Text

Proposed Tech Specs Revising Digital Instrumentation W/Analog Counterparts
	ML20083M831
Person / Time
Site:	Brunswick
Issue date:	01/26/1983
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20083M817	List: ML20083M814; ML20083M831;
References
	NUDOCS 8302010473
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11(D D o.

I:9 R2 5N O TABLE 2.2.1-1 (A(D h$ REACTOR PROTECTION SYSTEtt INSTRIltlENTATION SETPOINTS 28i3 ggD' ALIDWABLE g NCTIONAL UNIT AND INSTRUMENT NUMBER TRIP SETPOINT VALUES

1. Intermediate Range Monitor, Neutron Flux - liigh(II < 120 divisions of full scale < 120 divisions (C51-IRM-K60lA,B,C,D,E,F.G.It) of full scale

2. Average Power Range Monitor (CSI-APRM-Cll.A B C.D,E F) .

l a. Neutron Flux - liigh, 15%(2) < 15% of RATED TilERMAL POWER < 15% of RATED TilERMAL POWER 2 b. Flow-Biased Neutron Flux - Iligh(3)(4) < (0.66 W + 54%) < (0.66 W + 54%)

[ c. Fixed Fe.' tron Flux - liigh(4) < 120% of RATFD TilERMAL POWER < 120% of RATED TilERMAL POWER

3. Reactor Vesset Steam Dome Pressure - liigh < 1045 psig < 1045 psig

. (ti21-PTM-N023A-1.B-1 C-1,D-1)

.i

4. Reactor Vessel Water level - Low, level I ~

> +162.5 inches * ~

> +162.5 inches *

( li21 -LTri-N017 A- 1, B- 1, C- 1, D- 1 )

5. Main Steam Line Isolation Valve - Closure (5) < 10% closed < 10% closed (Ii21-F022A,B C.D; Il21-F028 A , B ,C . D) h 6. flain Steam Line Radiation - liigh < 3 x full power background < 3.5 x full power g, ( D 12-Ril-K603 A , B .C , D) background N

g 7. Drywell Pressure - liigh ~< 2 psig ~< 2 psig

( C 71 -PTil-N002 A- 1, H- 1, C-1, D- 1 )

8. Scram Discharge Volume Water level - High < 109 gallons < 109 gallons (Cl1-LSil-N013A,B C.D) ,*

(C l 1 -LSil-4 516 A , B , C , D) l

i

$ --TABLE 2.2.1-1 (Continued)

G y REACTOR PROTECTION SYSTEH INSTRIHtENTATION SETPOINTS q

' ALLOWABLE

--FullCTIONAL UNIT AND INSTRift1ENT NUMBER TRIP SETPOINT VALUES G

b 9. Turbine Stop Valve - Closure (6) < 10% closed l

< 10% closed e (EllC-SVOS-l X ,2 X ,3 X ,4 X) t 10 Turbine Control Valve Fast gsure, Control Oil Pressure - low > 500 psig > 500 psig (EllC-I SL-17 56,17 57,17 58,1759) 4 ,

IJ 4 L.n 4

a if b

i 3

us g2 TABI.E 3.3.1-1 (Continneil)

U

$ REACTOR PROTECTION SYSTEM INSTRUMENTATION O

APPLICABl.E MINIMUM NUMBER d OPERATIONAL OPERABI.E CilANNELS FilHCTIONAl. UNIT AND INSTittit!ENT NUMllER CONDITIONS PER TRIP SYSTEM (a) ACTION l

7. Drywell Pressure - liigli 1, 2(*) 2 6 (C71-PT-u002A,B,C,D)

(C 71-PTM-N002 A- 1, li- 1, C-1, D- 1 )

8. Scram Discitarge Volume llater Ixivel -

llidh 1, 2, 5(f) 2 5 (C i l -l.Sil-N013 A ,II ,C , D)

( C l 1 -LSil-4 516 A , B , C , D) l

9. Turbine Stop Val ve - Closure I ISI 4 8 y (EllC-SVOS-IX,2X,3X,4X)

, 10. Turblue Control Valve Fast Closure, Cont rol Oil Pressure - Low l(8) 2 8

( EllC-PSI.- 17 5 6,17 57,17 58,17 59) i1. Reactor Motle Switch in Shutdown Position 1,2,3,4,5 1 9 (C71A-51)

12. Itanual Scrata 1, 2, 3, 4, 5 1 10

( C71 -A-S 3 A , il) if

8 B-O,,

l m

o r

f

_ E d M e I ) r

_ Ts u d -

C n a S o e N c 6 8 m.l

_ O e 0 0 PS e S( 0 0 en E A A A A b n R N N f f N N lh a _

l c S a E h e H sh l t T e 8

mn i i

. ) S t d N t e O en u P se n S nn i E oo pp t R u s m o M eo C E R c

( T S c 2 Y .i

- S gn 1

i no

. i r 3 Or t t I sc 3 T ee

_ C tl .

8 K e .

l T e B O mt A R i s F P t r h i R g n ef O i o s

_ T i l i ne C t oh

_ A - i pt E , s s R l e b ef R e r I r o E V u B ) c s ) n mt M 1 I o 9 w ou U - l 5 o r p N r e C w7 d f n D. e r n1 t i T 1 t u tI , u t pe N - a s s 8 h E C, W ))

o) l X F a5 S ah et ll h 7 U e C 4, n x m D, D, g) 1 e1 R

i D, B i - er , i en T l u C,C, X vu7 oi S l s5 er e 3, C,1 , l h N o1 as7 c rf V 1, B, I - vX V e1 t a e B, A AA r a 2, l r , i D rA2 e36 l P6 w s o N u20 g1 1 VX o 5 S ) r A s00 s0N r05 aN4 p -

l rl 7 t i 1 e i B, a

ot t u T eN - h - - oS d) aA cp I r - H cliit t O nO o -. I oI r3 et N PTT s S. S. SV Cl S MS cS t u IL PP iI 1 S oP - S - eo l - - D - - e- er- rA A d l

l 1 1 1 1 nC nt C o1 l 1 r

\ e77 ml l i l l i n1 1 t 7 a7 no N wCC aCC bE b o8 cC uG ot 0 y( ( r(( r( rC( a( n( r c 1

c u u e a t e r 1 1

S T T R lf ut .

Gl k t

l e

f . . . I s li 0 2

. . . 1 F 7 1 1 9 1 I 1

w q i1, M $:;- , ._ !. s i *,r pp

(

r t!,

I!,

w p! TABI.E 4.3.1-1 (Continuetl) un y REACTOR PROTECTION SYSTEll itiSTRiltlENTATION SURVEILI.ANCE REQUIREMENTS O

, CilANNEL OPERATIONAL I'llNCTIONAl. IlNIT CilANNEl. FilNCTIONAL CilANNEL CONDITIONS IN WillCil d,_. Ai40 INSTRill!ENT NintilER CilECK TEST CAI.Il5 RATION (a) SURVEll. LANCE REQlllRED el

" % II.iin Steam 1.ine Isolation Valve - NA H R(I')

l I Closure

( ti21 -F02 2 A , B , C ,1) anil It21 -F028A , B ,C , D)

6. flain Steain 1.ine Railiation - 111 81: S M(I) R(3) 1, 2

( 012-R:1- K603 A , li ,C , D)

1. Drywell Pressure - liigli g ( C 71-PT-N 002 A , li,C , D) NA(k) NA R II) 1, 2

- ( C 71 -PT;l-NOO 2 A- 1,1$- 1,C- l , D-1 ) D ~H H 1, 2 Y

m ti . Scrain Discharge Volume Water f.evel - liigh NA Q R 1, 2, 5

( C l 1-1.Sil-N013A ,ll,C D)

( C i l- LSil-4 516 4, B , C ,1)) l

9. Turl>Ine Stop Val ve - Closure NA H !?(h) g (EllC-SVOS-l X.2X,3X 4X) 4 I tl. Torhine Control Valve Past Closure, Cont rol Oil Pressure -

1.o u NA 11 R 1 g ( EllC-PSI.-17 56, l / 57,17 58,17 59) g- 11. R act or lloite Sul tcli in Sluit< lown NA R NA 1,2,3,4,5 g Position n (C71A-SI) 4 ::

O l .d . II.inual Scrain NA Q NA 1,2,3,4,5

( G7 i A-S 3 A ,ll)

u q TAisLE 3.3.2-1 i/I Ej ISOLATION ACTUATION Ill3TRUllENTAT[0N O

, val.VE CROUPS !!INIMUM NUMiiER APPLICAllLE i

c- OPCRATED BY OPERAlll.E CilANNELS OPERATIONAL

.N i - - - - - - -TRIP FilNCTI0li AND INSTHil!!ENT NUMiiER SICNAI.(a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION

- " 1. PRlilARY CONTAIN!!ENT IS01.ATION

a. Reactor Vessel Water level -

1. Low, level 1 2, 6, 7, 8 2 1, 2, 3 20

( B 21 -I.T-N017 A- 1, B- 1, C- 1,0- 1 )

( 8 21 -I.TM-N017 A- 1, B- 1, C- 1, D- 1 )

2. I.ow , level 2 1, 3 2 1, 2, 3 20 (B21-1.T-N024A-1,B-1, and 821-LT-NO25A-I,B-1) b

, (B21-1/I'!!-N024 A-1, B-l asid y B21 -I!rti-N02 5 A- ! , B- 1 )

1 C

h. Drywell Pressure - Iligh 2, 6, 7 2 1, 2, 3 20 (C71 - PT-N002A , B ,C , D)

(C 71 -PTM-fl002 A- 1, B- 1, C- 1, D- 1 )

c. !!ain Steam 1.ine

1. Radiat ton - liigh (d) 1 2 1, 2, 3 21 (D12-1M-K603A,B C.D)

2. Pressure - Inu I 2 1 22 (il21 -PT-N015 A , B ,C , D)

. (il21-PTM-Nol5A-1,8-1 C-1,D-1) fi

@ 3. Flow - lif f,h 1 2/line 1 22

@- (ll21-PDT-N006A , B ,C , D;

@ B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,D;

'f' B 21 -PUT-N009 A , B ,C, D) .

( 1521-PDTM-N006 A- 1, B-I , C- 1, D- 1 ;

il21 - PDTM-fl007A-1, B- 1, C- 1, D-1 ;

il21 -PDT:1-N008A- 1, B- 1, C- 1, D- 1 ;

ll 21 - PD fil-flOO9A- ! , B- ! , C- 1, D-1 )

, TABLE _3.3.2-1 (Con t inuail) iA d ISOLATION ACTilATION lilSTRilMENTATION I!

, VAINE CRollPS HINIHLIll NUMilER APPLICABLE OPERATED BY OPERABLE CilANNELS OPERATIONAL

,d, -TR.I.P FilNCTION AND INSTRiftlENT NUMBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTION l'RiflARY CONTAINMENT ISOLATION (Continued) l it . H:iin Stea:n I.ine Tunnel Temperature - IIIgh 1 2(*) 1, 2, 3 21 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D; il21 -TS-N013 A , II , C , D) u e. Condenser Vacuum - Iow 1 2 1, 2 N) 21 2

3 ( B21 -PT-N0 56 A , B ,C , D) u (B21-PTH-N056A-1,B-1,C-1,D-1)

[ f. Turbine Building Area Temperature - liigh 1 4(e) 1, 2, 3 21 (B21-TS-322SA,B,C,D; B21-TS-3226A,B,C,D; il21 -TS-3227 A , II ,C , D ;

B21-fS-3228A,B,C,D; B21-TS-3229A ,15,C , D ;

B21-TS-3230A,B,C,D; il21 -TS-32 31 A , B ,C, D; B21-TS-3232A,II,C,D) it

'!n ii

'5

1

, TAsiLE 3.3.2-1 6I ki ISol.ATION ACTilA',floll ItdTRutlENTATION

, VALVE CRollPS titNIHilt! NLlHliER APPL.ICAlli.E OPERAIED liY OPERAlit.E CilANNELS OPERATlutlAL

,, T. K. i .l'. .l'_U.NC.f..l .ol_l __A..tl.D __IllSTRilflEtlT NiltillER

_ . _ SIGNAL.(:s) PER TRIP SYSTEll(b)(c) CotIDITION ACTIort

l. l'RiilARY CONTAltltit:NT ISOI.ATION

.. Reactor vessel Water level -

1. 1.aw , level 1 2,6,7,8 2 1, 2, 3 20

. . (1521 -1.T-N017 A- 1, B- 1, C-1, D- 1 )

( B 21 -1.TM-fl017 A- 1, B- 1, C- 1, D- 1 )

2. l .ow , lavel 2 1, 3 2 1, 2, 3 20 (1121 -1.T-H024 A-1, B-1, and B 21 -1.T-N02 5 A- 1, li- 1 )

b (li21-1.T:1-t1024 A-1,Il-l and 7* B 21 -1.f tl-fl02 5A- 1, ll- 1 )

i:

li . Drywell Pressure - liigh 2, 6, 7 2 1, 2, 3 20 .

( C 71 - PT-flD02 A ,ll ,C , D)

(C71-PTM-H002A-1,B-1,C-1,D-1)

c. !!.s in St eam 1.ine

1. Raitiation - Iligh (d) 1 2 1, 2, 3 21

( 012 -!*!!-l'603A , B ,C , 0)

, 2. Pressuru - low I 2 1 22

( B 21 -- PT-fl015 A , B , C ,0)

. ( 8 21 -P f;l-fl015 A- 1. h- ] , C- 1, D- 1 )

I j 3. Flow - lit P,li 1 2/line 1 22 j ( li21 -PDT-fl006 A , B ,C , D; j li21 -l'DT-i1007A , lI, C , D ;

1121 --l* DT-ilOO8A , B C . D; j 1121 -PDT-t1009A , B ,C, D)

( 1121 - PDTil-fl006 A- I ,11- ! , C- 1, D- I ;

!!21 - l'u l'H -ilOO 7A - l , B- 1, C-! , D- 1 ;

,~ 1121 -- l'D f:1-flOO8 A- I ,11- I , C- 1, D- I ;

B 21 - PD DI-fl009A-I , B-! , C-I , D-I )

TABI.E 3.3.2-1 (Continued) iA

$ MOLATION ACTUATION INSTRUMENTATION n

',' VAINE CROUPS MillIHutt NUtlBER ' APPLICAllLE OPERATED BY OPERAtti.E CllANNELS OPERATI0tlAL

'lj, R Il' FtlflCI'Ioti AND INSTRUt!ENT NUllllER SIGNAL (i PER TRIP SYSTEM (b)(c) CONDITIOri ACTION

1 i+ 2. SECONDARY CONTAIN!!ENT ISoIATION

a. Reactor llol1. ling Extianst Radiation - liigh 6 1 1, 2, 3, 5, and* 23

( D 12-R!i-N010A , B)

b. Drywell Pressure - liigh 2, 6, 7 2 1, 2, 3 23

, (C71-PT-r1002A,II C D)

( C 71 - PTI-t-11002 A- 1, il- 1, C- 1, D- 1 )

c. Reactor Vessel Water level -

3g I.o w , i.evel 2 1, 3 2 1, 2, 3 23 e (ll21-LT-fl024 A-1, B-l and u il21 -I.T-1102 5 A- 1, Il- 1 )

e ,-

w (ll21-1.Til-13024 A-1, B-1 and 821 -1.TM-Il02 5 A- 1. B- 1 )

a

'l . Hij }yTOR WATT'R Cl.EANIIP SYSTEl1 ISOLATION

. a. A Flo.: - lii gli 3 1 1, 2, 3 24 (G31-J FS-t1603-I A, l B)

b. Area Temperature - liigh 3 2 1, 2, 3 24 (G11-TS-Il600A,B,C D.E F)

, c. Area Ventilation A Temp. - lilgh 3 2 1, 2, 3 24 b,, (G31 -TS-N602A , il, C , D , E , F) h- d. SLCS initiation 3 (8) NA 1, 2, 3 24 g (C41A-SI)

,, e. Reactor Vessel Water Invel -

b' I.ow , level 2 1, 3 2 1, 2, 3 24 (ll21-1.T-fl024 A-1,B-l and 1121 -1.T-fl025 A-I , B- 1 ) ..

(il21-1.Til--Il024 A-1.B-1 and 821-IIDI-13025 A-1,B-1)

tn

! TAB!.:' 3.3.2-1 (Continued) p!

i U ISOLATION ACTUATION INSTRUtlENTATION 8

, VALVE GROUPS MINIMUM NUMBER APPLICABIE

, OPERATED BY OPERABIE CilANNELS OPERATIONAL j TitlP t'llflGr10N AND INSTatIMENT NUMilER SIGNAL.( a ) PER TRIP SYSTEM (b)(c) COM91 TION ACTION

1

- 4. CORK STANultY COOLING SYSTEMS ISOLATION

a. liigli Pressure Coolant Injection System Isolation

1. IIPCI Steam Line Flow - liigh 4 1 1, 2, 3 25 (E41-PDT-N004; E41-PDT-N005) '

o (E41-PDTS-N004-2; E41-PDTS-N005-2)

{ 2. IIPCI Steam Supply Pressure - low 4 2 1, 2, 3 25

( E41 -PS L-N00 l A , B ,C , D) b 3. IIPCI Steain Line Tunnel Temperature - liigh 4 2 1,2,3 25 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489)

4. tius Power Monitor NA(h) 1/ bus 1, 2, 3 26 f 5.

(E41-K55 and E41-K56)

IIPCI Turbine Exhaust h

g Diaphragm Pressure - liigh 4 2 1,2,3 25 n . ( E41 -l'Sil-N012 A , B ,0,0) o 6. IIPCI Steam I.ine Ambient Temperature - liigh 4 1 1, 2, 3 25 (E51-TS-N603C,D) ..

l' L

g TABLE 3.3.2-1 (Continued) d ISOLATION ACTUATION INSTRUMENTATION b VALVE GROUPS tlINIMUM NUMBER APPLICABLE 8

OPERATED BY OPERABLE CilANNELS OPERATIONAL 5 TRIP FUNCTION AND ltiSTRUMENT NUMBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTIOri U

g 7. IIPCI Steam Line Area A Temp. -

lii gh 4 1 1, 2, 3 25 l

(E51-dTS-N604C,D)

! 8. Emergency Area Cooler l Temperatiire - liigh 4 1 1, 2, 3 25 l l l (E41-TS-N602A,B) l l

b. Reactor Core Isolation Cooling System Isolation l

R*

I. RCIC Steam Line Flow - liigh 5 1 1, 2, 3 25

)

(E51-PDT-N017; y E51-PDT-N018) h (E51-PDTS-N017-2; E51-PDTS-No18-2)

2. RCIC Steam Supply Pressure - low 5 2 1, 2, 3 25

( E51 -PS-N019A , B , C , D)

3. RCIC Steam Line Tunnel Temperature

- liigli 5 2 1, 2, 3 25 (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; h E51-TS-3323; D E51-TS-3355; h E51-TS-3487)

N 4. Bus Power Monitor NA (h) 1/ bus 1, 2, 3 26 g (E51-K42 and E51-K43)

k TABLE 3.3.2-1 (Continued)

U gj ISOI.ATION ACTtIATION INSTRUMENTATION f'!

' V4LVE GR0 TIPS MINIttilM NilMBER APPLICABLE OPERATED BY OPERABl.E CIIANNELS OPERATIOriAl,

.i TRIP FilNCTION AtJD IrlSTRUMENT NUtillER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTION

.. 5. RCIC Turbine Exhaust Diaphragm Pressure - liigh 5 2 1, 2, 3 25 (E51 -PS-N012 A , B ,C , D)

6. RCIC Steam Line Asabient Temp -

liigh 5 1 1, 2, 3 25 (E51-TS-N603A,il) l

/. RCIC Steam Line Area A Temp - Iligh 5 1 1, 2, 3 25 l (E51-dTS-N604A 11)

M 8. RCIC E.piipment Roosa Asnbient Temp - liigh 5 1 1, 2, 3 25 Y (E51-TS-N602A,B) l

9. RCIC Equipment Rooin A Temp - liigh 5 1 1, 2, 3 25 (E51-dTS-N601A,B) l

5. SillirDollri COOLING SYSTEM ISOLATION

a. Reactor Vessel llater level -

Low, level 1 2,,6, 7, 8 2 1, 2, 3 27 (h21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1)

b. Reactor Steam Ibue Pressure- 7, 8 1 1, 2, 3 27 f,i !!!gh

$ ( B 32-PS-flO l 8A , B) li~

a n

U3 73 g __ tai!LE 3.3.2-2 I

.n y

IS01.ATION ACTalATION INS rRU!-lEffrATInti SETPOINTS A

ALLOWABl.E c-y' FilNCTION AND IriSTRiltlE!TT NUHilER TRIP SETPOINT VAI.U E d

H e- 1. Pd t!!ARY CONTAIN!!ENT ISOLATION

a. Reactor Vessel Water Level -

1. Inw, level I -> + 162.5 inches * ~> + 162.5 inches *

( B21 -Ilff t-N017 A- 1, ll- 1, C- 1, D- 1 )

2. loo, Level 2 ,

~> + 112 inches * ~> + 112 inches *

( H21-1.T!!-N024 A-1, B-l' and i B21-LTrl-NO2 5 A- 1, B- 1)

b. Drywel1 Pressure - liigh ~< 2 psig ~< 2 psig (C71 - PT!!-N0'12 A- 1, ll- 1, C-1 D- 1 ) )

j h y c. tiiin Steata 1.ine q 1. Radiation - liigh < 3 x full power background < 3.5 x full power (012-R:1-K603A,B,C D) background l l

2. Pressure - low ~> 825 psig ~> 825 psig ;

( il21 - PT!!-N015 A- 1, B- 1, C- 1, D-1 ) l

3. Flow - llidh < 140% of rated flow < 140% of rated flow

( ll 21 - P DT:1- N006 A- 1, B- 1, C- 1, D- 1 ;

B2 l-l'DTil-N007 A- 1, B- 1,C-! , D-1 ;

1121 - P DTri-N003 A- I , B- I , C- 1.D9 ,

B 21 -l'DTil-N009A- 1, n- 1, C- 1, D- 1 )

tI m

i' M

R Y

,e '

' ' ' ' ' ' ' ' ' ' - - ' ~ - -

LJ p! TABLE 3.3.2-2 (Continued)

ISOI.ATION ACTllATION lilSTRUrlENTATION SETPOINTS n

v:

, AI.LOWABI.E

,y ._FR.I P._F__il_llCT._ ION AND I_NST_Rll!!ENT NUf1BER

_ __ _ TRIP SETPOINT _VAI.llE N PHillARY CONTAINilENT IS01.ATION (Continued) t'

d. flain Steam I.ine Tunnel Temperature - Iligh < 200*F < 200*F

(!!21-TS-N010A , B ,C , D; 1 l B21-fS-NOIIA,B,C,D; l B21-TS N012A,B,C D; B 21-TS-N013 A , il , C , D)

e. Condenser Vacuum - Iow > 7 inches lid vacuum > 7 inches lig vacuum u (321-PTft-N056A-1,B-1,C-1,D-1)

N f. Turbine Buil ling Area Temp - Illgh < 200*F < 200*F y (il21 -TS-3225 A , il ,C , D; g B21-TS-3226A,B,C,D; il21 -TS-3227A , B ,C , D ;

1121-TS-32 28 A , B .C . D ;

1121-TS-3229A,B,2,n; B21-TS-3230A,B,C,D;

!!21 -TS-3211 A , B , C , D; il21-TS-3212 A ,it ,C , D)

2. SECONDARY CONTAINilENT IS01.ATION

a. Reactor Bull. ling Exhaust y Raillation - liigh < 11 mr/hr < 11 mr/hr g (D12-Ilf t-N010A , B) ,

h b. Drywell Pres.;ure - liigh < 2 psig < 2 psig g (C71 - PT!!-N002 A- 1, ll- 1, C- 1. D- 1 )

3" c. Reactor Vessel Water Imvel -

+ 1.o w , level 2 > + 112 inches * > + 112 inches *

(1121-I.T?l-NO24 A-I ,15-I and 1521 -1.Tri-1102 5 A- 1, B- 1 )

un p! TAllt.E 3.3.2-2 (Continued)

ISOLATION ACTilATION INSTRUMENTATION SETPOINTS O

ALL0llABLE T_R_IP FullCr.i_ori AllD INSTRiltlENT NUZ!!!ER TRIP SETPOINT VAI.llE U 3. HEACTOR tl4TER Cl.EANUP SYSTEM ISOLATION

a. A Flou - liigh ~< 53 gal / min ~< 53 gal / min (G31-d FS-fl603-I A, i B)

b. Area Temperature - liigh -< 150*P -

< 150*F (G31-TS-fl600A B.C D.E F)

c. Area Ventilation Temperature A Temp - liigh < 50*F < 50*F (G 31 -TS-fl602 A ,11, C , D, E , F)

d. St.CS Ini t iat ion NA NA h (C41A-SI) u e. Reactor Vessel ifater level -

b Lou, lave 1 2

~

> + 112 inches * ~

> + 112 inches *

(ll21-LT!!-fl024 A-1, B-l and li21-LT!!-!102 5 A- 1, B- 1 )

4. Col:E STANDfiY C001.IllG SYSTEMS ISOLATION

a. liigh Pressure Coolant Injection System Isolation

1. IIPCI Steam Line Flow - liigh < 300% of rated flow < 300% of rated flow

( E41 -PDTS-II004-2 ;

E4 l-Po rs-fl005-2 )

i-g 2. IIPCI Steam Supply Pressure - Low > 100 psig > 100 psig g ( E41 -PS L-t1001 A , B , C , D) h 3. IIPCI Steata 1.i ne Tunnel Temperatnre - liigh < 200*F < 200*F u (E41-TS-3314;

., E41-IS-3315;

,o' ' E41-TS-3316; E41 -TS- 3 317 ;

E41 -TS-3 318 ; ..

E41-rS-3354; E41-rS-3488; E41 - rS- 3489 )

<n g TABLE 3.3.2-2 (Continued) i Li

$ ISOLATION ACTUATION INSTRilhENTATION SETPOINTS O ALLOUABLE TRIP FlitJCTION AND INSTRutlENT NUf1BER TRIP SETPOINT val.U E M

H 4. Bus Power Monitor NA NA

" (E41-K55 and E41-K56)

, 5. IIPCI Turbine Exhaust Diaphragm Pressure - liigh < 10 psig < 10 psig (E41-PSil-N012 A , B ,C , D)

6. IIPCI Steam 1.ine Ambient Temp - I!!gh < 200*F < 200*F (E51-TS-N603C,D)

7. IIPCI Steam Line Area A Temp - liigh < 50*F < 50*F m (E51-dTS-N604C,D)

D 8. Emergency Area Cooler Temp - llidh < 175*F < 175*F

'f (E41-TS-N602A,B)

O

b. Reactor Core Isolation Cooling System Isolation

1. RCIC Steam 1.Ine Flow - liigh < 300% of rated flow < 300% of rated flow

( E 51- PDTS-N017-2 ; i l

E51-PUTS-N018-2)

2. RCIC Steam Supply Pressure - Iou 50 psig > 50 psig l

( E51 -PS-N019A , B , C , D)

3. RCIC Steam 1.Ine Tunnel Temp - liigh < 175*F < 175*F (E51-TS-3319;

. E51-TS-3320;

$, E51-TS-3321; 3 E51-TS-3322; h E51-TS-3323; 5 E51-TS-3355;

,, E51-TS-3487) j o'

4. Bus Power !!onitor NA NA (E51-K42 and E51-K43) ..

i TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRU:iENT NUMBER RESPONSE TUIE (Seconds)#

1. PRDIARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Ievel -

1. Iow, Level 1

<13 (B21-LT-N017A-1,B-1,C-1,D-1) ~

(B21-LTM-N017A-1,B-1,C-1,D-1)

2. Low, Iavel 2

<1.0**

(B21-LT-N024A-1,B-1 and ~

B21-LT-N025A-1,B-1)

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1)

b. Drywell Pressure - High <13 (C71-PT-N002A,B C.D)

(C71-PTM-N002A-1,B-1,C-1 D-1)

c. Main Steam Line

1. Radiation - High* ~<1.0**

(D12-RM-K603A,B,C,D)

2. Pressure - Low <13 (B21-PT-N015A,B,C,D) ~

(321-Prt-N015A-1,B-1,C-1,D-1)

3. Flow - High <0.5**

(B21-PDT-N006A,B,C,D; ~~

B21-PDT-N007A,B,C D; B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C,D)

(B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1)

d. Main Steam Line Tunnel Temperature - High (B21-TS-N010A,B,C,D; ~<13 B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D)

e. Condenser Vacuum - Low <13 (B21-PT-N056A.B.C,D)

(B21-PTM-N056A-1,B-1 C-1,D-1)

BRUNSWIC:(-UNIT 1 3/4 3-22 . Wend =ent No.

T l

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)l)

PRI:G1Y CONTAINMENT ISOLATION (Continued)

f. Turbine Building Area Temperature - High NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-IS-3228A,B,C,D; B21-TS-3229A,B C D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)

2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Exhaust Radiation - High* j:13 (D12-RM-N010A,B)

b. Dryvell Pressure - High <13 (C71-PT-N002A,B,C,D) ~~

(C71-PTM-N002A-1,B-1,C-1,D-1)

c. Reactor Vessel Water Level - Low, Level 2 <1.0**

(B21-LT-N024A-1 B-1 and ~~

B21-LT-N023A-1,3-1)

(B21-LTM-N024A-1,B-1 and B21-LIM-N025A-1,B-1) ~

~

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - High j:13 (G31-dFS-N603-1A,13)

b. Area Temperature - liigh <13 (G31-TS-N600A,B,C,D,E,F) ,

c. Area Ventilation Temperature AT - High ;(13 (G31-TS-N602A,B,C,D,E,F)

d. SLCS Initiation NA (C41A-S1)

e. Reactor Vessel Water Lavel - Low, Level 2 <1.0**

(B21-LT-N024 A-1, B-1 and ~~

B21-LT-N025 A-1,B-1)

(B21-LT:t-N024 A-1,3-1 and 821-LTM-N025 A-1,B-1) 3RUNSWICK - UNIT 1 3/4 3-13 Amendment :;o .

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TI:iE (Seconds)#

4. CORE STANDBY COOLING SYSTEMS ISOLATION

a. High Pressure Coolant Injection System Isolation

1. HPCI Steam Line Flow - High ~

<13 (E41-PDT-N004; E41-PDT-N005)

(E41-PDTS-N004-2; E41-PDTS-N005-2)

2. HPCI Steam Supply Pressure - Low jgl3 (E41-PSL-N001A,B,C,D)

3. HPCI Steam Line Tunnel Temperature - Righ <13 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 4 Sus Power Monitor NA (E41-K55 and E41-K56)

5. HPCI Turbine Exhaust DLaphragm Pressure - Iligh NA .

(E41-PSH-N012A,B,C,D)

6. HPCI Steam Line Ambient Temperature - High NA (E51-TS-N603C,D)

7. HPCI Steam Line Area NA (E51-dTS-N604C,D)

8. Emergency Area Cooler Temperature - Iligh NA

- (E41-TS-602A, B)

b. Reactor Core Isolation Cooling System Isolation

1. RCIC Steam Line Flow - High NA (E51-PDT-N017; E51-PDT-N018)

(E51-PDTS-NOI'-2; E51-PDTS-N018-2)

2. RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,0) 3 RUNS'itCK - CNIT I 3/; 3-24 Amendment !!o .

i TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

3. RCIC Steam Line Tunnel Temp - High NA (E51-IS-3319; E51-TS-3320; E51-TS-3321; E51-IS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487)

4. Bus Power Monitor NA (E51-K42 and E51-K43)

5. RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-PS-N012A,B,C,D)

6. RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A,B)

7. RCIC Steam Line Area a Temp - High NA (E51-dTS-N604A,B)

8. Emergency Area Cooler Temperature - High NA (E51-TS-N602A,B)

9. RCIC Equipment Room A Temp - liigh NA (E51-dTS-N601A,B)

5. SHUTDOWN COOLING SYSTEM ISOLATION

a. Reactor Vessel Water Level - Low, Level 1 - NA (B21-LT-N017A-1,B-1,C-1,D-1)

(B21-LTM-N017A-1,B-1,C-1,D-1)

b. Reactor Steam Dome Pressure - High NA (B32-PS-N018A,B)

Radiation monitors are exempt from response time testing. Response cime shall be measured from detector output or the input of the first electronic component in the channel.

- Isolation actuation instrumentation response time only.

1 Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to tsolation time shown in Table 3.6.3-1 and Table 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTCt RESPONSE TIME for each valve.

SRUNSWIC: - ONIT ! 3/4 3 -2 '.a Amendment :;o .

us y FABl.E 4.3.2-1 iA

$ ISOLATI0ti ACTilATIOri INSTRll!!ENTATION SURVEILLANCE REQllIREllENTS il

, CllANNEL OPERATIONAL

,_. CilANNEl. FiltlCTION AL CllANNEL CONDITIONS Ill WillCll d

a rRIe FilNCr10N AND INSTRUtlENT nut!BER CllECK TEST cal.IBRATION SilRVEILLANCE RdQUIRED H

1. PRIllARY C0!1rAINilEtiT I S01.ATION

a. Reactor Vessel Water level -

1. Iow, Icvel 1

( 821 -1.T-N017 A- 1, B- 1, C- 1, D- 1 ) NA(a) NA R(b) 1, 2, 3

(!!21 -LT!!-N017 A- 1, B- 1, C- l , D- 1 ) 1) H H 1, 2, 3

2. Inw, level 2 (B21-LT-N024A-1,B-1 and o B21-LT-!!O25A-1,B-1) NA NA R 1, 2, 3 N (B21-LTri-N024A-1,B-1 and j' B21 -I.Tri-N02 5 A- 1, B- 1 ) D M M 1, 2, 3

h. Drywell Pressure - liigh (C71-PT-NOO2A,B,C,D) NA(a) NA R(b) 1, 2, 3

( C71 -PT!!-fl002 A- 1, B- 1, C- 1, D- 1 ) D ?! H 1, 2, 3

c. !!ain Steara 1.ine

1. Railiat ion - liigh D W R 1, 2, 3

( D 12-R!!-K60 3A , B ,C , D)

2. Pressure - low

( B 21 -PT-No l 5 A , B ,C , D) NAI ") NA R(b) 3 (ll21 -PTN-fl015 A- 1, B- 1, C- 1, D- 1 ) D !! M i

'p - 3. Flow - liigh

( B 21-PI)T-N006A , B ,C , D; NA(") NA R(b) g g Il21 -PDT-fl007 A , B .C . D; g Il2l-PDT-N008A,B,C,D;

" B21-Pl>T-N009A,B,C,D)

,o ( B 21 -PDTel- N006 A- 1,8-1, C- I , D- 1 ; i) H H 1

!!21 -PDT!!-NOO7 A- ! , B- 1, C- 1, D- I ;

I!21 -PDTil-N008A- 1, B- 1, C-1, D- 1 ; . ..

B21-PDT:1-N009A-1,B-1,C-1,D-1)

TABLE 4.3.2-1 (Continued)

A ISOI.ATI0ti- ACTUATION INSTRutlENTATION SURVEILLANCE REQUIREllENTS j

[}

, CllANNEL OPERATIONAL CilANNEL FUNCTIONAL CllANNEL Cot!DITIGNS IN WilICil N.. TR i a* FUNCTIO!! AND INSTitHNENT NUMilER CilECK TEST CALIBRATION SURVEII.I.ANCE REQUIREI)

H 8"

gillARY CONTAltlHENT IS01.ATION (Continued)

.l . !Liin Steam Line Tunnel Teinperatore - Iligh IIA H R 1, 2, 3

( il21 -TS-fl010A , B ,C ,0 ;

B21-TS-fl011 A , B ,C ,D; il21-TS-fl012 A , B , C , D ;

il21-TS-flO l 3 A , B , C , D)

e. Cointenser V.icuum - lau h ( B 21-PT-fl05 6 A , B , C , D) liA(a) NA R(b) 1, 2#

( Il21 -PTil-N05 6 A- 1, B- 1, C- 1, D- 1 ) D H H 1, 2#

8g f. Turlitae Building Area Temp-liigh NA H R 1, 2, 3

( Il21 -TS-32 25 A , B ,C , D; B21-TS-32264,il,C,D; Il21-TS-3227A.II C D; B 21 -TS-3228 A , II ,C ,0 ;

il21 -TS-3229 A ,II ,C , D ;

il21-TS-3230A,B,C,D; Il21 -TS-3231 A , ti ,C , D; B21-TS-3232A,B,C,D) fi" e s

9 0

n

]

L

( A3 p TABLE 4.3.2-1 (Continued) d U IS01.ATION ACTilATION INSTRt! MENTATION SURVEILLANCE REQllIREMENTS M

CilANNEL OPERATIONAL CllANNEL FUNCTIONAL CilANNEL CONDITIOrlS Ill 11:1IC11

[j,

} TRIP FilHCTION AND IriSTRUIlENT NUMBER CilECK TEST _ CALIBRATION SURVEII. LANCE REQtilREO e-1

& 2. SECONOARY CONTAIll!!ENT ISOLATION

a. !!eactor fluilding Exhailst Radiation - liigh D M R 1,2,3,5, and *

(D12-R!!-H010A , B)

b. Drywell Pressure - liigh

( C 71-PT-t1002A , B ,C , D) NA Na R 1, 2, 3

( C 71 -PT!!-N002 A- 1, B- 1, C- 1, D- 1 ) D M M 1, 2, 3

c. Reactor Vessel Water Invel -

% Iow , i.evel 2 (B21-LT-N024 A-1,ll-1 and NA(") NA R(b) 1, 2, 3

,i, B21-LT-fl025 A-1,B-1)

(B21-LTM-11024 A-1, B-I and D M M 1, 2, 3 B21-L'Ill-NO25 A-1, B-1)

3. REACCOR WATER Cl.EANilP SYSTEl-1 ISOLATION

a. A Flow - liigh D M R 1, 2, 3 (G 31-J FS-N603-1 A, l B)

b. Area Temperature - liigh NA M R 1, 2, 'l (G31-TS-N600A,B,C,D,E,F)

, c. Area Ventilation A Temp - liigh NA M R 1, 2, 3

( (C 31 -TS-fl602 A ,11,C , D , E , F) f

.l . SLCS Initiat ton fiA h R NA 1, 2, 3 g (C41A-SI)

", e. Reactor Vessel Water level -

il low , Level 2 (ll21-LT-NO24 A-1,B-1 and NA(a) NA R ID) 1, 2, 3 li21-LT-NO25 A-1,B-1) ..

(ll21-LTH-Ilo24 A-1,ll-1 and D M M 1, 2, 3 il21 -LT!!-N02 5 A- 1, B- 1 )

tu

--TABI.E 4.3.2-1 (Continued)

U ISOI.ATION ACTUATION INST _ RUllENTATION SURVEII. LANCE REQUIREMENTS

@ CilANNEL OPERATIONAL i CllANNEL FUNCTIONAL CilANNEL CONDITIONS IN NilICil g TRIP FilNCTION AND INSTRUMENT NilHBER CilECK TEST CALIBRATION SURVEILLANCE REQlllRED M

H

4. -CORE STANDBY C001.ING SYSTEMS ISOLATION e

liigh Pressure Coolant Injection System Isolation a.

1. IIPCI Steam Line Flow - liigh (E41-PDT-N004; NA(a) NA R(b) 1, 2, 3 E41-PDT-N005)

(E41-PDTS-N004-2; D M M 1, 2, 3 E41-PDTS-N005-2) u 2. IIPCI Steam Supply Pressure -

3 Low NA !! R 1, 2, 3 (E41-PSL-N001 A , B ,C . D) s 3. iiPCI Steam Line Tunnel Temperature - liigh NA M 1, 2, 3 Q

(E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3388; E41-TS-3489) k 4. Bus Power Honitor NA R NA 1, 2, 3 E.

n (E41-K55 and E41-K56)

@ 5. IIPCI Turbine Exhaust Diaphragm Pressure - liigh NA M Q 1, 2, 3 (E41 -PSil-Ho l 2 A , B ,C , D)

6. IIPCI Steam Line Ambient ..

Ten.p - Iligli NA H R 1, 2, 3 (E51-TS-N603C,D) j

s f tai!LE 4.3.2-1 (Continue.1) is y ISOLATION ACTil4 TION INSTRUMEi4TATION SURVEII.I.ANCE REQUIREllENTS O

CilANNEL OPERATIONAL

[, CilANNEL FUNCTIONAL CllANNF.L CONDITIONS IN LlillCil d TRIP filNCTION AND lilSTituilENT NUM13ER CilECK TEST CAI.IBRATION SURVEll.l.ANCE REQllIRED

?$

e 7. lil>CI Steam Line Area A Temp - liigh NA H R 1, 2, 3 (E51-dTS-N604C,D)

8. I'mergency Area Cooler Temp - liigh NA H Q 1, 2, 3

( E41 --TS-N602 A , B)

b. Reactor Core Isolation Cooling System Isolation u 1. !!CIC Steam 1.Ine Flow - liigh D (E51-PDT-N017; NA(d) NA R ID) 1, 2, 3 g.2 E51 -PDT-11018)

I U (E 51-PDTS-t1017-2 ; D M M 1, 2, 3 (E51-PDTS-N018-2)

2. RCIC Steam Supply Pressure - Inw NA H Q 1, 2, 3

( E 51 - PS-N019A ,il ,C , D)

3. RCIC Steam Line Tunnel liigh Temperature NA N R ; , 2, 3 (E51-TS-3319; ESI-TS-3320; E51-TS-3321;

,i f E51-TS-3322; O E51-TS-3323; '

lI ESI-TS-3355;

$ E51-TS-3487) o u

4. lius Ibuer !!anitor NA R NA 1, 2, 3 (E51- K42 anil E51-K43)

5. RCIC liirhine Exhaust ..

Diaphragm Pressure - liigh NA H R 1, 2, 3 (E51-PS-N012A,B,C,D)

CJ p TAllt.E 4.3.2-1 (Continued) d h ISOLATION ACTUATION INSTRU lEfffATION SilRVEILI.ANCE HEQUIREMENTS El

, CilANNEI. OPERATIONAL

, CilANilEL FUNCTIONAL CilANNEL CONDITIOris IN WilICil d T K i t' FUNCTION AND 164STHUtlENT NilMBER CllECK TEST CALIllRATION SilRVEILIANCE REQilIRED U

- 6. RCIC Steam 1.ine Anblent Temp - liigh NA 11 R 1, 2, 3 (E51-TS-N603A,B)

7. RCIC Steam I.ine Area A Temp - liigh NA M R 1, 2, 3 (E 51-dTS-N604 A ,li)

8. RCIC h<luipment Room Ambient Temp - liigh NA M Q 1, 2, 3 g (E51-TS-N602A B)

9. RCIC E41uipment Room A Temp - liigh NA M Q 1, 2, 3 e

p (E51-dTS-N601A,B)

'2 . SilllTD0tJN COOLING SYSTEM ISOLATION

a. Reactor Vessel Water lxvel -

Low, i.evel 1

( B 21-l.T-N017 A- 1, B-1,C-1, D-1 ) NA(") NA R(b) 1, 2, 3

( B 21 -1.Til-fl017 A- 1, B- 1, C- 1, D- 1 ) D M M 1, 2, 3

b. Reactor Steam Ibue Pressure -

Iligh NA S/U(c) ,M R 1, 2, 3 g (ll32-PS-N018A , B) 8 m

tihen handling irradiated fuel in the secondary containment.

S // 11 hen reactor steam pressure > 500 psig.

u (a) The transmitter channel checE is satisfied by the trip unit channel check.

A separate transmitter check is not required.

(1,) Transiaitters are exempted from the monthly channel calibration.

(c) Il not performed within the previous 31 days.'

uJ y2 TABLE 3.3.3-1 u

EMEllCENCY CORE COOLING SYSTEtt ACTUATION INSTRUMENTATION O

MINIMl!M NU!!bER APPLICABLE OPERABLE CalANNELS OPERATIONAL TRIP, FilflCTION AND IflSTitilllENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION e -- 1. ColtE St RAY SYST.E._tt

a. Reactor Vessel Water level - low, Level 3 2 1,2,3,4,5 30 -

( 1521 -LT-fl031 A , B , C , D)

(B21-LTS-NO31A-4,B-4,C-4,D-4) l> . Reactor Steam lhme Pressure - low (Injection Per.nissive) 2 1, 2, 3,4,5 31 (1121 -PT-NO21 A , B ,C , D)

(15 21-PTS-N021 A-2, B-2,C-2,D-2)

c. Drywell Pressure - liigh 2 1, 2, 3 30 l (El1-PT-N01IA,B,C,D) u (E l 1-PTS-fl011 A-2, B-2,C-2,0-2) d, .l . Time Iblay Relay

" 1 1,2,3,4,5 31 (E21-K16A,B)

e. lius Power th>uitor# 1/ bus I,2,3,4,5 32 (E21-KI A,is)

2. l.0W PRESSURC COOLANT INJECTION MODE OF RilR SYSTEM l

a. Drywell Pressure - liigli 2 1, 2, 3 30 (E l l-PT-N0 l l A , B ,C , D)

( E l 1 -PT!!-i10 l l A- 1,11-1, C-1, D-1 ) -

l> . Reactor Vessel Water level - Iow, Level 3 2 1, 2, 3, 4*, 5* 30

!I (!!21 -LT-fl031 A , B ,C , D)

$ (1121 -LTS-s1031 A-4, B-4,C-4, D-4 )

R to e. Reactor Vessel Shroud level (Drywell Spray Permissive) 1 1, 2, 3, 4*, 5* 31 3 (ll21-LT-NO36 and il21-LT-NO37) b (B21-LTM-NO36-I and 1121-LTM-NO37-1)

d. Reactor Steam ihme Pressure - low (Injection Periaissive)

( B 21 -PT-N02 i A , B , C , D) ..

(ll21-PTt-i1021A-1 B-1,C-1,D-1)

( B 2 l-PTS-NO21 A-2,15-2, C-2, D-2 )

1. RilR Pump Start and LPCL Injection Valve Actuation 2 1, 2, 3, 4*, 5* 31

2. Recirculation Inop Pump Discharge Valve Actuation 2 1, 2, 3, 4*, 5* 31 I

C1 23

.9 --.-TAtiLE 3.3.3-1 (Continued) y EMERGENCY CORE C001.ING SYSTEM ACTUATION INSTRUMENTATION v

e MINIMUti NUMBER APPLICA15LE

,q OPERA BlE CilANNEl.S OPERATIONAL M TRI* FilNCTION AND INSTRUMENT NUMi!ER PER TRIP SYSTEM CONDITIONS ACTION

1 1.OW PRESSURE COOLANr INJECTION H0DE OF RllR SYSTEM (Continued) l

e. RilR Pump Start - Time Iblay Relay 1 1, 2, 3, 4*, 5* 31 (STR-1Al,2 and STR-lill ,2 )

f. lius Power :tanitor# 1/ bus 1, 2, 3, 4*, 5* 32 (EIl-KlO6A,B)

{ 3. lilGil PRESSURE COOLANT INJECTION SYSTEM l

j. a. Reactor Vessel Water level - low, Level 2 2 1, 2, 3 30 t- (1121-LT-NO3 I A , B ,C , D)

(B21-LTS-Il031 A-2, B-2,C-2,D-2)

h. Drywell Pressure - Iligh 2 'i , 2, 3 30

( E l l-PT-N0 l l A , B ,C , D)

(Ell-PTS-NollA-2,il-2,C-2,D-2)

e. Condensate Storage Tank 'v e - low 2** 1, 2, 3 33 (E41-LS-fl002. E41-LG-N00' )

.l . Suppression Chamber Water lavel - liigh 2** 1, 2, 3 33 (E41-LSil-fl01 SA , B)

,. e. Bus Pawer :tonitor# 1/ bus 1, 2, 3 32 (o (E41-K55 and E41-K56) ,

(a 4. AllTOMAT I C ,DEPR ESSUR I Z AT IOt3 SYSTEM l N a. Drywell Pressure - liigh, coincident with 2 1, 2, 3 30 M (El1-PT-N010A,B,C,D)

. ( B 1 1- PTH-t1010 A- I ,11- 1, C- ! , D- 1 )

h. I:eactor Vessel Water level - low, Level 3 2 1, 2, 3 30 (li21-LT-UO31 A ,li,C , D)

( t!21-LTS-NO 31 A-3, B-3, C-3, D-3 )

UJ N TA!!IE 3. 3. 3-1 (Continued) rl n

EMERGENCY CORE COOLING SYSTElf ACTUATION INSTRUMENTATION n

, tilNIMUti NUMBER APPL.ICAllLE OPERABLE CllANNELS OPERATIONAL

.' id, TRIP Flir4CT10N AND INSTRllt!ENT NUMilER PER TRIP SYSTEH CONDITIONS ACTION AllThiltTIC DEPRES':URIZATION SYSTEtt (Continued) l

c. Reactor Vessel Water level - law, level 1 1 1, 2, 3 30 -

(1521-LT-N04 2A , B)

(B21-LTH-N042A-1,B-1)

.l . ADS Timer 1 1, 2, 3 31 (ll21-TDPil-KSA , B)

e. Core Spray Pinap Discharge Pressure - liigh (Permissive) 2 1, 2, 3 31 (E21-PS-N008A,B and E21-PS-N009A,B)

f. RilR (LPCI 11008) Pump Discharge Pressure - I!!gh (Permissive) 2/ pump 1, 2, 3 31 y (El1-PS-N016A,B,C,D and E l 1 -PS-NO20A ,II,C , D)

g. Lins Pawer lionitor# 1/ bus 1, 2, 3 32 (ll21-KI A , ti)

APPLICAi1LE TOTAL. NO. CilANNEl.S HINIHilM CilANNELS OPERATIONAL FutNTidriAL llNIT OF CilANNELS TO TRIP OPERABIE CONDITIONS ACTION

5. 1.0SS OF POWER 1,

a. 4.16 kv Emergency tius 1/ bus 1/ bus 1/ bus 1,2,3,4##,5## 34

,8 tladervoltage (Loss of u voltage)

b. 4.16 kv isnergency lius 3/ bus 2/ bus 2/ bus 1,2,3,4##,5## 35

" llade rvol tano (IMgraded y Voltage)

tb t applicable when two core spray system subsy' stems are OPERAllLE per Specification 3.5.3.1.

- Provides signal tu itPCI pump suction valves only. ,

Ala rra only.

1. Re< pit red when ESF equipmeut is required to be OPERABli.

LQ q TABLE 3.3.3-2 i.s M EMERGENCY CORE COOLING SYSTEtt ACTUATION INSTRUMENTATIOri SETPOINTS O

, AI.LOWAlli.E Td l.P. FUllCT.I.O.N. AND IrlSTRU!!ENT NUMilER TRIP SETPolN_T_ VALUE g -- _

s

'i

1. CdRE SPRAY SYSTEll e

a. Reactor Vessel Water Level - law, Iavel 3 -

> + 2.5 inches * -> + 2.5 inches *

(1521-LTS-r1031 A-4,B-4, C-4,D-4) .

h. Reactor Steam Dmae Pressure - low 410 + 15 psig 410 + 15 psig

(!!21-PTS-N021 A-2, B-2,C-2,D-2)

c. Drywell Pressure - liigli --< 2 psig -< 2 psig

( E l l-PTS-t10 l l A-2, B-2, C-2, D-2)

.t . Time Delay-Relay 14 < t < 16 secs 14 < t < 16 secs M (E21-K16A,B) s-o e. ilus Power llanitor NA NA 8, (E21-KI A ,ll) 4-

2. 1.00 PRESSURE C001. ANT IN.IECTION MODE OF Rillt SYSTEM l

a. Drywell Pressure - liigh < 2 psig < 2 psig

( E l l -PT!!-fl0 l l A- 1, B- 1, C-1,D- 1 )

12 Iteactor Ves.sel Water level - Low, Level 3 -> + 2.5 inches * > + 2.5 inches *

~

(ll21-LTS-:n 314-4, B-4, C-4,D-4 )

c. Reactor Vessel Shrouil level > - 53 inches * > - 53 inchea*

(ll21-LT 1-fl036-1 and U21-LTM-NO37-1)

k. it . Reactor Steam Dome Pressure - Iow n

y- 1. RilR Pump Start anal I. CPI Valve g Actuation 410 f 15 psig 410 + 15 psig

" ( B 21 -P l's-rlo21 A-2, B-2, C-2, D-2)

,o 2. Recirculation Pump Discharge Valve Actuation 310 i 15 psig 310

15 psig (Il21-PTil-fl02 i A-1,ll-1,C-1,D-1) ,.

ta FJ d TAlli.E 3.3.3-2 (Continued) en

$ EMERGENCY CORE C001.ING SYSTEll ACTilATION INSTRUMENTATION SETPOINTS D

, AI.LOWAllt.E r, _r_R.I_l> tillNCTIOd Arlo IrlSTRll!!ENT tlUMilER _ TRIP SETPOINT VAI.llF.

g -

ut.1 enSSSIINE Co0I. ANT ItlJECTION ?! ODE OF RilR SYSTEM (Contlaned) l

e. RilR Pump Start - Time iblay Relay 9<t< 11 seconds 9<t < 11 seconds (STR-1Al,2 and ST R-Illi ,2 )

t' . lius Power Manitor NA NA (El1-K106A,B)

3. IIIGil PRESSl1RE Cool. ANT IrlJECTION SYSTEM

a. Reactor Vessel Water level - Iow, level 2 > + 112 inches * > + 112 inches

p ( B 21 -1.TS-fl0 31 A-2, B-2, C-2, D-2 )

y h. Drywell Pressure - liigh < 2 psig < 2 psig P> (E I 1 -PTS-fl0 I 1 A-2,11-2, C-2, D-2)

c. Condensate Storage Tank tavel - Iow (E41-1.S-N002; E41-1.S-N003)

-> 23 feet 4 inches -

> 23 feet 4 inches

.l . Suppression Chamber Water level - liigh -< -2 feet ** -

< -2 feet **

( E41 -1.Sil-fl015 A , II)

c. Hus P.)wer Monitor NA NA (E41-K55 an.1 E41-K56)

4. AllT0!!ATIC Del'RESSilRIZATION SYSTEM l

, a. Drywel 1 Pressure-liigh < 2 psig < 2 psig

{l, (El1-PT!!-N010A-t,8-1,C-1,D-1) o

[j b. Reactor Vessel Water level - Iow, level 3 > + 2.5 Inches *

> + 2.5 inches

i g (It21 -1.TS-Il031 A-3, B-3,C-3, D-3)

[', c. Reactar Vesael Water level - Iow, Invel 1 __> + 162.5 inches

__

> + 162.5 inches *

,U ( 1521 -1.TM-fl04 2 A- 1, B- 1 )

.l . AlsS Timer

( t! 21 -TD PtJ-K 5A , li) < 120 seconds < 120 seconds

w y TABLE 3.3.3-2 (Continued) il

$ EMERGENCY CORE C00LIfC SYSTEtt ACTUATION INSTRUMENTATION SETPOINTS O.

, Al.LOWAHLE

- TRIP FlJtlGTION AtlD If1STRiltlENT NiltlBER TRIP SETPOINT VAllIE

k. !

AllrOHiTIC DEPRESSilRIZATION SYSTEM (Continued)

e. Core Spray Pump Discharge Pressure - tilgh > 100 psig > 100 psig (E21-PS-fl008A,B and E21-PS-N009A,B)

f. RllR (LPCI 110DE) Pump Discharge Pressure - liigh > 100 psig > 100 psig (Ell-PS-N016A,B,C,D and El1-PS-N020A,B,C,D)

g. Ilus Power Monitor NA NA t ,2 (il21-Kl A , B) 4=

t .> 5. _ LOSS OF POWER E a. 4.16 kv Isaergency Bus lladervoltage a. 4.16 kv Basis - 2940

161 volts 2940 i 315 volts (loss of Voltage)# h. 120 v Basis - 84 i 4.6 volts 84 i 9 volts

c. i 10 sec, time delay 1 10 secs. time delay

h. 4.16 kv ILnergency Bus lindervoltage a. 4.16 kv Basis - 3727 i 9 volts 3727 i 21 volts (Oegraded Voltage) b. 120 v Basis - 106.5 i 0.25 volts 106.5 i 0.60 volts

c. la t 0.5 sec. time delay 10 i 1.0 sec. time delay 55 8

R m

y # This is an inverse time delay voltage relay. The voltages shown are the maximum that will not result

- in a trip. Lower voltage conditions will result in decreased trip times.

Vessel water levels refer to REFERENCE LEVEL ZERO.

- Suppression chamber water level zero is the toIns centerline minus I inch.

!$ TAllLE 4.3.3-1 0

$ EMERGENCY CORE C001.ING SYSTEtt ACTilATION INSTRUMENTATION SURVEILLANCE REQlIIRE!!ENTS N

M CilANNEL OPERATIONAL CilANNEL FilNCTIONAL CilANNEL C0tIDITIONS IN WilICil Tulf FilNCTInti AND lilSTRUME!4T NUtlBER CllECK TEST CALIliRATION

]!

.i SURVEILI.ANCE REQUIRED

1. C]RE SPRAY SYSTEM

a. Reactor Vessel Water level - .

Inw, I.evel 3

( H 21 -l.T-N O 31 A , B ,C , D) NA( ) NA R(b) 1, 2, 3, 4, 5 (1521 -1.TS-NO 31 A-4, B-4, C-4, D-4 ) D !! H 1, 2, 3,4,5 13 . Reactor Steam Irime Pressure - law (il21 -PT-N021 A,ll,C , D) NA(d) NA R(D) 1, 2, 3,4,5 (il21-PTS-NO21A-2,B-2,C-2,D-2) D M M 1, 2, 3, 4, 5

- c. Drywell Precsure - liigh

" (El1-PT-N011A,n,C,D) NA(") NA R(b) 1, 2, 3 7 ( E l l- PTS-fl0 l l A-2, B-2, C-2, D-2 ) D ti M 1, 2, 3

.l . Time fulay Relay NA R R 1, 2, 3, 4, 5 (E21-K16A . II)

e. lius Power Mani tor NA R NA 1, 2, 3, 4, 5 (E21-KI A,ll)

2. l.tM PRESSURE COOLANT INJECTION MODE OF RilR SYSTEM l

a. Drywel L Pressure - liigh

( E I l-P T-N011 A ,II,C, D) NA

) NA R 1, 2, 3 (El 1-Pftt-t101 I A-1, B-1,C-1,D-1) D H H 1, 2, 3 ,

.- is . Reactor Vessel Water Invel -

k, Inu, level 3 8 ( n 21 -l.T-NO 31 A , n , C , u) NAC ^) NA R(b) 1, 2, 3, 4*, 5*

M (ll21 -lirS-H031 A-4, B-4,C-4, D-4) D 11 M 1, 7 3, 4*, 5*

u

c. Reactor Vessel Shr<2 nit level ti o (il21-LT-NO36 and il21-LT-NO37) NA(a) NA R(b) I , 2, 3, 4*, 5*

(Il21-LTtt-flul6-1 au l H21-LTM-NO37-1) D H H 1, 2, 3, 4*, 5*

I I

fN TAllLE 4.3.3-1 (Continued)

, j EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS I CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil TR i s' l'UtlCTIori AND It4STRUMENT NUMBER CliECK TEST CALIllRATION SURVEILLANCE REQUIRED

],

e. i g PRESSURE COOLANT INJECTION MODE OF RilR SYSTEM (Continued) l

d. Reactor Steam Ibue Pressure - Low NA(a) NA R(b) 1, 2, 3, 4*, 5A (B21-PT-N021A,B,C,D)

1. RilR Pump Start and LPCI Injection Valve Actuation D M M 1, 2, 3, 4*, 5*

(1121-PTS-N021A-2,B-2,C-2,D-2)

! 2. Recirculation loop Pump

Discharde Valve Actuation D M M 1, 2, 3, 4*, 5*

(B21-PT!!-fl021 A-1, B-1,C-1,D-1)

}

u e. RilR Pump Start - Time Iblay Relay NA R R 1, 2, 3, 4*, 5*

b (STR-lAl.2 and STR-IB1,2)

f. lius Power Monitor NA R NA 1, 2, 3, 4*, 5*

(El1-K106A,B)

3. It!Gil PRESSURE C00LANf INJECTION SYSTEM l

a. Reactor Vessel Water level -

Inw, Level 2 (B21-LT-NO31A,B,C,D) NA(a) NA R(b) 1, 2, 3 (B21-LTS-NO31A-2,B-2,C-2,D-2) D M M 1, 2, 3

'fi li . Drywell Pressure - llid h

.$ (El1-PT-N011A,B,C,D) NA(a) NA R(b) 1, 2, 3 l} (Ell-PTS-N0llA-2,B-2,C-2,D-2) D H H 1, 2, 3 m

S c. Condensate Storage Tank level - low NA M Q 1, 2, 3 u (E41-LS-N002; E41-LS-N003) o l il . Suppression Chamber Water level - liigh NA M Q 1, 2, 3

( E41 -LSit-No 1 SA , B) .*

e. Bus Power Monitor NA R NA 1, 2, 3 (E41-K55 and E41-K56)

4 l

., a ,

hj nitLE 4.3.3-1 (Continued)

O

] E!!ERGENCY CORE COOLING SYSTEM ACTilATION instill!MENTAT10tl SilRVEILLANCE REQllIREllENTS o

Ct!ANNEL OPERATIONAL 8

CllANNEL FilNCTIONAL CllANNEL CONDITIONS IN Wi!ICl!

G TRiv FilNCfl0!I AND IllSTRllMENT NllMBER CliECK TEST CALIllRATION SilRVEILLANCE REQll! RED 7 -

,, 4. AllTullA flC DEPRESSl!RIZATION SYSTEM l

a. Drywell Pressure - liigli *

( E l 1 -PT-N010 A , B ,C ,1)) NA(^) NA R(b) 1, 2, 3

( E l l - t'TM-N010 A- 1, B- 1, C- 1, D- 1 ) D H H 1, 2, 3 l b. Reactor Vessel Water level -

Inu, level 3 (15 21 -LT-NO 31 A ,11, C , D) NA(a) NA R(b) 1, 2, 3

(!!21-LTS-NO31 A-3,8-3,C-3,D-3) D M M 1, 2, 3

e. Reactor Vessel Water level -

low, level I

'; ' (1521-LT-N042 A,il) HA(3) NA R(b) 1, 2, 3

( ll21-LTM-N0 4 2 A- 1, B- 1 ) D !! M 1, 2, 3

d. ADS Timer NA R R 1, 2, 3 (li21 -TDPU-KSA ,ll)

e. Core Spray Pump Discliarge Pressure - 1118:1 NA M Q 1, 2, 3 (E21-PS-N008A,Il and E21-PS-N009A,il)

t. KilR (LPCI MODE) Pump Discliarge Pressure - 1113 1: NA M Q 1, 2, 3

., (Ell-PS-N016A,B,C,D and

[8 El1-PS-N020A,B,C,D) n

[j- p, . lius Power Moni tor NA R NA 1, 2, 3

@ (ll21 -K I A,11) ft

to

q TABLF. 2.2.1-1 M

$* REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS S

, ALLOWABI.E FUNCTIONAL UNIT AND INSTRUMENT NUMBER TRIP SETPOINT VALUES t

U l. Intermediate Range !!onitor, Neutron Flux - liigb(I) < 120 divisions of full scale < 120 divisions 82 (C51-IRM-K601A,B,C,D,E,F,C,II) of full scale

2. Average Power Range !!onitor (CS I-april-Cll. A , B ,C ,D ,E , F)

a. ticutron Flux - liigh, 15%(2) < 15% of RATED TilERMAL POWER < 15% of RATED TilERMAL POWER

b. Flow Blased Neutron Flux - liigh(3)(4) < (0.66 W + 54%) < (0.66 W + 54%)

rg c. Fixed Neutron Flux - liigb(4) < 120% of RATED TilERMAL POWER < 120% of RATED e

TilERMAL POWER

3. Reactor Vessel Steam Dome Pressure - liigh < 1045 psig < 1045 psig (B21-PTM-N023A-1,B-1,C-1,D-1)

4. Reactor Vessel Water Imvel - low,14 vel I > +162.5 inches *

-> +162.5 inches *

(ll21 -LT!!-N017 A- 1, B- 1, C- 1, D- 1 ) -

5. Main Steam Line Isolation Valve - Closure (5) < 10% closed < 10% closed (ll21 -F022 A , B ,C , D ;

B21-F028A,B,C,D) g 6. !!ain Steam Line Radiation - Iligh < 3 x full power background < 3.5 x full power g (D12-RM-K603A,B,C,D) background P-N 7. Drywell Pressure - Iligh

~

< 2 psig -< 2 psig S (C72-PTil-N002A-1,B-1,C-1,D-1)

8. Scram Discharge Volume Water Level - litgh < 109 gallons < 109 gallons

( C l 2-1.Sil-N013 A , B ,C , D)

(C l 2-LSit-4 516A , B ,C , D)

N O TABLE 3.3.1-1 (Continneil)

TA REACTOR PROTECTInti SYSTEM INSTRilMENTATION s

APPLICABLE MINIMUM NUMBER G OPERATIONAL OPERABLE CilANNELS j j FilNCTIOfiAL UNIT AND INSTRUMENT nut 1BER CONDITIONS l'ER TRIP SYSTEM (a) ACTION l l 7. Drywell Pressure - liigh 1, 2(*) 2 6 (C72-PT-N002A,B,C,D)

(C72-PTt1-N002A-I,B-!,C-1,D-1) -

H. Scram Discharge Volume Water Level -

liigh 1, 2, 5(f) 2 5

( C l 2-LSii-N013 A , B ,C , D)

( C l 2-LSil-4 516 A , B , C , D)

U

9. Turbine Stop Valve - Closure 1 ("> ) 4 8 1

( EllC-SVOS-l X ,2 X ,3X,4X)

Y

10. Turbine Control Valve l'ast Closure, Control Oil Pressure - Law 1(8) 4 8

( EllC-PS L-1756,17 57,1758,1759)

I1. Reactor Made Switch in Shutdown Position 1,2,3,4,5 1 9 (C72A-SI)

12. Manual Scram I,2,3,4,5 1 10 (C72A-S3A,B) ii B

n 1

w p TABLE 3.3.1-2 (Continued) d vi

$ REACTOR PROTECTION SYSTEM RESPONSE TIMES O

, RESPONSE TIME g t'lltJGTiotJAI. UNIT AND INSTRUMENT NUf!BER (Seconds)

M H 7. Drywell Pressure - llidh NA sa ( C7 2-PT-N002A ,8,C , D)

(C 7 2-PTH-11002 A- 1, B- 1, C- 1 D- 1 )

8. Scram Discharge Volume Water level - liigh NA

( C l 2-LSt!-N013 A , B ,C . D)

(C l 2-LSit-4 516A , B ,C , D)

') . ' turbine Stop Valve - Closure < 0.06

( EllC-SVOS-I X ,2 X ,3X ,4 X)

E t-

10. Turbine Control Valve Fast Closure, < 0.08 u Control Oil Pressure - low h ( EllC-PSL-1756,17 57,17 58,17 59)

I1. I:eactor Mode Switch in Shutdown Position NA (C72A-SI)

12. Manual Scram NA (C72A-S3A,B)

IAutron detectors T.re exempt from response time testing. Response time shall be measured from letector output or from the input of the first electronic component in the channel.

'c' R

E o

TABLE 4.3.1-1 (Continued) ii n REACTOR PROTECTION SYSTEM __INSTRlltiENTATION SURVEILLANCE REQUIREt1ENTS P:

, CilANNEL OPERATIONAL

c. FilNCTIONAL UNIT CilANNEL FilNCTIONAL CllANNEL CONDITIONS IN tillICil

j A_N._i s_ INSTittillENT Nll!!8ER CllECK TEST CALIBRATION (a) SURVEILI.ANCE REQUIRED g --

' " 5. !!ain Steam Line Isolation Valve - NA M R(h) 1 Closure (B21-F022A,B,C,D and B21-F028A,B,C,D)

6. !L In Steam Line Radiation - liigh S M(I) R U) 1, 2 (D12-R!t-K603A,B,C,0)

7. Drywell Pressure - liigh NA(k) R II) t' (C72-PT-N002A,d.C D) NA -

1, 2 (C72-PT1-N002A-1,B-1,C-1,D-1) D H H 1, 2 Y

2'

8. Scrain Discharge Volume Water Level - liigh NA Q R 1, 2, 5 (C l 2-LSit-N013 A , B ,C , D)

(C l 2-LSil-4 516.1, B ,C , D)

9. Turbine Stop Valve - Closure NA M R(h) g (ElC-SVOS-lX,2X,3X,4X)

10. Turbine Control Valve Fast 4 Closure, Control Oil Pressure -

Inw NA M R 1 h ( EllC-PS L-17 56,17 57,17 58,17 59)

E

) P, 11. Reactor Mode Switcli in Shutdown NA R NA 1,2,3,4,5 i

@ Position (C72A-SI)

U

12. Ilanual Sc rain NA Q NA 1, 2, 3,4,5 (C72A-S34,B) a

h TABl.E 3.3.2-1 h ISOLATION ACTUATION INSTRilt!ENTATION n

' VAINE GROUPS HINIMUt! NUMBER APPLICABLE OPERATED BY OPERAlli.E CilANNELS OPERATIONAL

, TRIP FUNCTION AND INSTRiit!ENT NUMBER SICNAI.(a) PER TRIP SYSTEM (b)(c) CONDITION ACTION

.i s2 1. NIllARY CONTAIN!!ENT ISOLATION *

... Reactor Vessel Water level -

1. Iow, level 1 2,6,7,8 2 1,2,3 20 (B21-LT-N017A-1,B-1,C-1,D-1)

( B21 -LTil-N017A- 1, B- 1, C- 1, D-1 )

2. Low , lavel 2 1, 3 2 1, 2, 3 20 (B21-LT-N024A-1,B-1, and B21-LT-N025A-1,B-1) ,

D (B21-LTil-NO24A-1, B-I and u

B21-I.TM-N025A-1,B-1)

" 1, . Drywell Pressure - liigli 2,6,7 2 1, 2, 3 20 (C7 2-PT-N002 A , B ,C , D)

(C72-PrM-N002A-1,B-1,C-1,D-1)

c. !!ain Steam Line

1. Radiation - Iligh (d) 1 2 1, 2, 3 21

( 012-RM-K603 A , B ,C , D)

2. Pressure - Iow 1 2 1 22 (B21-PT-N015A,B C.D)

( 8 21 -PTil-No l 5 A- 1, B-1, C-1 D-1 )

k 3. Flow - liigh 1 2/11ne 1 22 (B21-PDT-N006A,B,C,D;

{.

to 821-PDP-N007A,B,C,0; 5 il21-PDT-N008A , B ,C , D ;

B21-PDT-N009A,B,C,D)

( B 21 - PDT!!-fl006 A- 1, B- 1, C- 1, D- 1 ;

1121 -PDTil-!1007A- 1, B- 1, C- 1, D- 1 ;

ll21 -l'DTM-tiOO8 A- 1, B- 1, C- 1, D- 1 ;

B 21 -P DTil-N009A- 1, B-1, C-1, D-1 )

I w

p TABLE 3.3.2-1 (Continueil)

!I

$ ISOLATION ACTUATION INSTRUMENTATION 9

, VALVE GROUPS lIINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CIIANNELS OPERATIONAL d

H p lP FI)NCTION AND INSTRiltlENT NUffBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTION igilARY CONTAIN!!ENT IS01.ATION (Continued)

4. Flow - liigh 1 2 2, 3 21 (B21-PDTS-N006A-2; B21-PDTS-N0078-2; B21-PDTS-N008C-2; il21-P!)TS-N009D-2 )

d. !!ain Steam Line Tunnel Ter9perature - liigh 1 2I *) 1, 2, 3 21 4

y (I!21-TS-N010A,B,C D; B21-TS-N01IA,B,C,D; i B21-TS-N012A,B,C,D; e5 !!21-TS-N013A,B,C,D)

e. Condenser Vacuuia - low 1 2 1, 2(f) 21

( B 21-PT-N056 A , B ,C , D)

(B21-PTM-N056A-1,B-1,C-1,D-1)

f. Turbine Building Area Temperature - Iligh 1 4I *) 1, 2, 3 21 (B21-TS-3225A,B,C,D; B 21- TS-3226 A , B ,C , D; B21-TS-3227A,B,C,D; I!21-TS-3228A,B,C,D; k il11-TS-32 29A , B ,C, D ;

g '

.ll-TS-3230A,B,C,D; o B21-TS-3231A,B,C,D; E

n I!21-TS-3232A,B,C,D)

TAtlLE 3.3.2-1 (Continued)

M ISOLA _T_ ION ACTilATION INSTRUMENTATION

, VALVE GROUPS HINIHilti tillMBER APPLICABLE OPERATED fly OPERAllLE CilANNELS OPERATIONAL y,_, TRIP FUNCT[0N AND IllSTKilMENT NL:MllEtt S IGNAI.( a ) PER TRIP SYSTEM (b)(c) CONDITIOfi ACTION

1 s> 2. SECONilARY CONTAINt1ENT ISOLATION

a. Reactor Building Exhaust Radiation - liigh 6 1 1, 2, 3, 5, and* 23

( 012-RM-fl010A , B)

h. Drywell Pressure - liigh 2, 6, 7 2 1,2,3 23

( C72-PT-II002 A , B ,C , D)

(C72-PTH-fl002A-1 B-1,C-1,D-1)

c. Reactor Vessel Water Level -

e low , lavel 2 1, 3 2 1, 2, 3 23 J (1121-LT-NO24A-1,B-1 and og B 21-l.T-Ilo2 5 A- 1, li-1 )

C (1521-LTM-N024 A-1,B-1 and B21-LTri-N025 A- 1, B-1 )

3. REACTOR WATER CLEANtJP SYSTEH ISOLATION

a. A Flow - liigh 3 1 1, 2, 3 24 (G31-d FS-N 603-1 A, l B)

h. Area Temperature - liigh 3 2 1,2,3 24 (G31-TS-N600A,B,C,D,E,F)

, c. Area Ventilation A Temp. - liigh 3 2 1, 2, 3 24 g, (G31-TS-il602A,B,C D.E F) h d. St.CS Initiation 3 (g) NA 1, 2, 3 24 (C41A-SI) f, e. Reactor Vessel Water level -

o' Lou, tavel 2 1, 3 2 1, 2, 3 24 (li21-LT-t!024 A-1, B-1 and 1521-LT-NO2 5 A-1, B-!) ,.

(ll21-LT!!-N024 A-1,B-1 and B21-LTH .1025 A-!,B-1)

TABIE 3.3.2-1 (Continued)

h y ISOLATI0il ACTilATIOl{ INSTRUMENTATION n

, VALVE GROUPS IIINIMUtl NUMBER APPLICAB12 OPERATED BY OPERABIE CllANNELS OPERATIONAL d TRIP l'UNCfl0N AND INSTRUllENT NUMBER SICHAL(al PER TRIP SYSfEM(b)(c) CONDITION ACTION se 4. Ct)RE STANDisY COOLING SYSTEMS ISOLATION

a. liigh Pressure Coolant Injection System Isolation

1. IIPCI Steam Line Flow - liigh 4 1 1, 2, 3 25 (E41-PDT-N004; E41-PDT-N005)

(E41-PDTS-N004-2; E41-PDTS-N005-2)

2. IIPCI Steaia Supply Pressure - Low 4 2 1, 2, 3 25 g (E41-PSL-N001 A,B,C,D)

C y- 3. IIPCI Steata Line Tunnel Temperature - liigli 4 2 1, 2, 3 25 (E41-TS-3314; E41-TS-3315; '

E41-TS-3316; E41-TS-3317; E41-TS-3118; E41-TS-3354; E41-TS-3488; E41-TS-3'89)

.., 4. Bus Power Monitor NA II') 1/ bus 1, 2, 3 26 h (E41-K55 and E41-K56) h 5. IIPCI Turbine Exhaust g Diaphragia Pressure - liigh 4 2 1, 2, 3 25 et ( E41-PSil-No l 2 A , B ,C ,0) t:

,o 6. IIPCI Steata Line Ambient Temperature - llidh 4 1 1, 2, 3 25 (E51-TS-N603C,D) ..

l

.% 3 TAHl.E 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUllENTATION n

VAINE CROUPS tlINIMUtl NUMBER APPLICABI.E j, OPERATED BY OPERABLE CIIANNELS OPERATIONAL d TR i ta FUNCTION AND INSTRUllENT NUMBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITI0tl ACTION H

a2 7. IIPCI Steam Line Area A Temp. -

4 liigli 4 1 1, 2, 3 25 (E51 ilTS-N604C,D) l

8. Emergency Area Cooler Temperature - liigli 4 1 1, 2, 3 25 l (E41-TS-N602A,B)

h. Reactor Core Isolation Cooling System Isolation u 1. RCIC Steam Line Flow - liigh 5 1 1, 2, 3 25 D (E51-PDT-N017; u

E51-PDT-N018)

C (E51-PDTS-N017-2; E51-PDTS-No18-2)

2. RCIC Steam Supply Pressure - Lou 5 2 1, 2, 3 25 (E51-PS-N019A,B,C,D)

3. RCIC Steam Line Tunnel Temperature

- liigh 5 2 1,2,3 25 (E51-TS-3319; E51-TS-3320; E51-TS-332!;

E51-TS-3322; 6 E51-TS-3323;

$ E51-TS-3355; l}

n E51-TS-3487) 3 4. Bus Pawer Honitor NA (h) 1/ bus 1, 2, 3 26 ,

(E51-K42 and E51-K43) e'

TABLE 3.3.2-1 (Continued) is y ISOLATION ACTUATION INSTRUMENTATION n

VALVE CROUPS tlINIllUtt flUMiiER APPLICABLE

,c; OPERATED llY OPERABLE CilANNELS OPERATI0tlAL

.; - . .TRI P FIINCT.IO_N_ APID lilSTRUMEllT NUtillER SICNAI(a) PER TRIP SYSTEM (b)(c) C0tIDITION g _

_A_.CT_ ION

'2

5. RCIC Turbine Exhaust Diaphragm Pressure - liigh 5 2 1, 2, 3 25

( E 51 -PS-fl012 A , B , C , D)

6. RCIC Steam Line Ambient Temp -

liigh 5 1 1, 2, 3 25 (E51-TS-fl603A , B) l

7. RCIC Steam 1.ine Area A Temp - liigh 5 1 1, 2, 3 25 (E 51-dTS-fl604 A , B) l

8. RCIC Equipment Room Ambient Temp - liigh 5 1, 2, 3 25 u 1 l

j.

1 (E51-TS-N602A,B) o.

9. RCIC Equipment Room A Temp - liigh 5 1 1, 2, 3 25 l (E51-dTS-N601A,B)

5. SilUTDOWN COOLING SYSTEM ISOLATION

a. Reactor Vessel Water Imvel -

Low, level 1 2,6,7,8 2 1, 2, 3 27

( ll21 -LT-fl017 A- 1, B- 1, C- 1 D- 1 )

( ll21 -LTil-N017 A- 1, il- 1, C- 1, D- 1 )

. b. Reactor Steam ihme Pressure- 7, 8 1 1, 2, 3 27 lj liigh

( 83 2-PS-N018:\ , B)

E n

w p TABLE 3.3.2-2 .

?l fj ISOLATION ACTUATION INSTRUMENTATION SETPOINTS O

ALLOWABLE

h. gl*, FuflCTION AtJD INSTRil!!ENT NUMllER TRIP SBTPOINT VAtllE a

la 1. PKliLARY CONrAINtlENT ISOLATION

a. Reactor Vessel Water level -

1. Io w , tevel I > + 162.5 inches * > + 162.5 inches *

( B 21-1.Til-N017 A- 1,8- 1, C- 1, D- 1 )

2. Iow , level 2

> + 112 inches * ~

> + 112 inches *

(B21-LTil-NO24A-1,B-1 and B 21-1, rM-tiO 2 5A- 1, B-1 )

b. Drywell Pres.sure - liigh < 2 psig < 2 psig 3 ( C7 2-PTri-t1002 A- 1, B- 1, C- 1,D- 1 )

y c. flain Steam Line q 1. Radiation - liigli < 3 x full power background < 3.5 x full power

( D 12-II:1-K603 A , B ,C , D) background

2. Pressure - low > 825 psig > 825 psig (ll21-PTM-Nol5A-1,B-1,C-1,D-1)

3. Flow - liigh < 140% of rated flow < 140% of rated flow

( ll21-PDTil-N006 A- 1, B- 1, C- 1, D- 1 ;

!!21-PDTil-N007 A- 1, B-1, C-! , D-1 ;

il21-PDT!!-N008 A- 1, B- 1, C- 1, D- 1 ;

il21- PDTil-N009 A- 1, B- 1, C- 1, D-1 )

4. Flos - liigli < 40% of rated flow < 40% of rated flow h (B21-PDTS-N006A-2; n B21-PD rS-N00711-2 ;

h Il21-PDTS-N008C-2; o B21-PirrS-N0090-2)

Y l

i TABl.E 3.3.2-2 (Continued) d kl ISOI.ATION ACTUATION INSTRU!!ENTATION SETPOINTS AI.I.0WABl.E g IRIP l'illlCTION AfID IHSTRiff!ENT NUMBER TRIP SETPOINT val.llE

,, _PRlillRY__ CONTAIN!!ENT ISOLATION (Continued) l el. }l. tin Steam I.ine Tunnel Temperature - liigh < 200*F < 200*F (Is 21 -TS-N010A ,8,C , D; 1121 -TS-N01 1 A , II ,C , D ;

il21-TS N012A,B,C,D; B21-TS-N013A,B,C,D)

e. Condenser Vacuum - low > 7 inches lig vacuun > 7 inches lig vacuum

( B 21 -PTM-N0 56 A- 1, il- 1, C- 1, D- 1 )

f. Tiirbine Building Area Temp - Iligh < 200*F < 200*F y ( B 21 -TS-3225 A , il ,C , D; y ll21 -TS-322 6 A , is ,C , D ;

B21 -TS-322 7A ,li ,C , D ;

il21 -TS-3228 A , B ,C ,0 ;

il21 -TS-3229A , B ,C , D ;

B21-TS-32304,II,C,D;

!!21-TS-32 31 A ,11,C,D; il21-TS-3232A,B,C,D)

2. :jEC0!!DARY CONTAlti!!ENT ISOLATI0l4

a. Reactor 11allding Exhaust h Radiation - liigh < 11 mr/hr < 11 mr/hr

@ (D12-l!Il-NO I OA ,11) n ij b. Drywell Pressure - liigh < 2 psig < 2 psig

,3 (C 72- PT!!-fl002 A- 1, li- 1, C- 1, D- 1 )

y c. Reactor Vessel Water level -

1.ow , tevel 2 > + 112 inches * > + 112 inches *

(!!21-I.Til-flo24 A-1,B-1 and

~

Il21 -tirM-Il025 A- 1, B- 1 )

l'ABLE 3.3.2-2 (Continued) id IS01.ATION ACTIJATIOff INSTRll!!ENTATION SETPOINTS

, ALLOWABLE TRIP FilflCTION AND I!1STRilf!ENT NUMBER TRIP SETPOINT VALUE

3. M ACTOR WATER Cl.EANUl' SYSTEM ISOLATION

a. A Flow - liigh < 53 gal / min < 53 gal / min (G31-dFS-N603-1A,lB)

b. Area Temperature - liigh < 150*F < 150*F (C31-TS-N600A,B,C,D,E,F)

c. Area Ventilation Temperature A Temp - liigh < 50*F < 50*F (G31-TS-N602A,B,C,D,E,F) u d. SLCS Initiation IIA NA

} (C41A-SI) y e. Reactor Vessel Water level -

3 Low, level 2 > + 112 inches * > + 112 inches *

(1121-LTit-NO24 A-I , B-1 and '

ti21-LTM-N025 A- 1, B- 1 )

4. CORE STAND 15Y COOLING SYSTEMS ISOLATION

a. Iligh Pressure Coolant Injection System Isolation

1. IIPCI Steam Line Flow - liigh < 300% of rated flow < 300% of rated flow (E41-PDTS-N004-2; E41-PDTS-fl005-2)

g 2. IIPCI Steam Supply Pressure - low > 100 psig > 100 psig g (E41-PSL-N001A,B,C,D)

{I 3. IIPCI Steam Line Tunnel Temperature - liigh < 200*F < 200*F 0, (E41-TS-3314;

,, E41-TS-3315;

,o' E41-TS-3316; E41-TS-3317; E41-TS-3318; ..

E41-TS-3354; E41-TS-3488; E41-IS-3489)

TAILLE 3.3.2-2 (Continued)

ISOLATION ACTllATION ltlSTRUMENTATION SETPOINTS ALLOllAllLE rdlP,FLINCFION At3D lllSTRullENT NUilllER TRIP SETPOINT VALUE

4. Bus Power Monitor NA NA sa (E41-K55 and E41-K56)

5. IIPCI Turbine Exhaust Diaphragm Pressure - liigh < 10 psig < 10 psig

( E41 -PSit-11012 A , B ,C , D)

6. IIPCI Steam Line Ambient Temp - liigh -< 200*F -

< 200*F (E51-TS-N603C,D)

7. IIPCI Steam Line Area A Temp - liigh ~~< 50*F -

< 50*F (E51-dTS-N604C,D)

H. Emergency Area Cooler Temp - liigh < 175*F < 175*F u (E41-TS-11602A , B)

L

h. Reactor Core Isolation Cooling System Isolation

1. RCIC Steam Line Flow - liigh < 300% of rated flow < 300% of rated flow (E51-PDTS-NG17-2; E51-PDPS-N018-2)

2. RCIC Steam Supply Pressure - Low > 50 psig > 50 psig (E51-PS-N0194,B,C,D)

3. RCIC Steam Line Tunnel Temp - liigh < 175*F < 175*F (E51-TS-3319;

, E51-TS-3320;

!T E51-TS-3321; k

. ti E51-TS-3322; E51-TS-3323; E

E51-TS-3355;

, , E51-TS-3487)

/. Ilus Paaer Munitor NA NA (E51-K42 and E51-K43) .

TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

1. PRIMARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level -

1. Low, Level 1

<13 (B21-LT-N017A-1,B-1,C-1,D-1) ~~

(B21-LTM-N017A-1,B-1,C-1.D-1)

2. Low, Level 2

<l.0**

(B21-LT-N024A-1,B-1 and ~~

B21-LT-N025A-1,B-1)

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1)

b. Drywell Pressure - High (C72-PT-N002A,B,C,D) j:13 (C72-PTM-N002A-1,B-1,C-1,D-1)

c. Main Steam Line

1. Radiation - High* ,,1.0**

(012-RM-K603A,B,C,D)

2. Pressure - Low <l3 (B21-PT-N015A,B,C,D) --

(B21-PTM-N015A-1,B-1,C-1 D-1)

3. Flow - High < 0.5**

(B21-PDT-N006A,B,C,D; B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C.D; B21-PDT-N009A,B,C,D)

(B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1,D-1:

B21-PDT.9FN008A-1. B-1, C-1, D-1 ;

B21-PDT:1-N009A-1,B-1,C-1,D-1)

4. Flow - High <0.5**

(B21-PDTS-N006A-2; -~

B21-PDTS-N0073-2; B21-PDTS-N0080-2; B21-PDTS-N0090-2)

d. Main Steam Line Tunnel Temperature - High <13 (321-TS-N010A,B,C,D; ,

B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B.C.D)

e. Condenser Vacuur - Low <13

( B21-PT-N056/ . 3,C, D) --

( B 21-PT:1-N056A-1,3-1, C-1, D-1 )

3RU::SWIC:;-UNIT 2 3/4 3-22 \mendr.2e nt No .

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#

PRIMARY CONTAIN:iENT ISOLATION (Continued) l

f. Turbine Building Area Temperature - Righ NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)

2. SECONDARY CONTAINMENT ISOLATION

+

a. Reactor Building Exhaust Radiation - High* -<13 (D12-RM-N010A,B)

b. Drywell Pressure - High j_:13 (C72-PT-N002A,B,C,D)

(C72-PTM-N002A-1,B-1,C-1.D-1)

c. Reactor Vessel Water Level - Low, Level 2 <1.0**

~~

(B21-LT-N024A-1.B-1 and B21-LT-N025A-1,3-1)

(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) ~

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - High j_:13 (G31-dFS-N603-1A,1B)

b. Area Temperature - High <13 (G31-TS-N600A,B,C,D,E,F)

c. Area Ventilation Temperature AT - High <13 (G31-TS-N602A,B,C,D,E,F)

d. SLCS Initiation NA (C41A-SI)

e. Reactor Vessel Water lavel - Low, Level 2 <1.0**

(B21-LT-N024 A-1,3-1 and 821-LT-N025 A-1 B-1)

(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1,3-1) 3RUNSWICK - UNIT 2 3/4 3-23 Amendment 'b .

TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)i/

4. CORE STAND 3Y COOLING SYSTEMS ISOLATION

a. High Pressure Coolant Injection System Isolation

1. HPCI Steam Line Flow - High ~

<13 (E41-PDT-N004; E41-PDT-N005)

(E41-PDTS-N004-2; E41-PDTS-N005-2)

2. HPCI Steam Supply Pressure - Low <13 (E41-PSL-N001A,B,C,D)

~~

3. HPCI Steam Line Tunnel Temperature - High "-<13 (E41-TS-3314; E41-TS-3315; E41-IS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS - 3489 )

4 Sus Power Monitor NA (E41-K55 and E41-K56)

5. HPCI Turbine Exhaust Diaphragm Pressure - ,,

High NA (E41-PSH-N012A,B,C,D)

6. HPCI Steam Line Ambient Temperature - High NA i (E51-TS-N603C,D) l l

7. HPCI Steam Line Area NA (E51-dTS-N604C,D)

8. Emergency Area Cooler Temperature - High NA (E41-TS-602A,B) j b. Reactor Core Isolation Cooling System Isolation

1. RCIC Steam Line Flow - High NA (E51-PDT-N017; E51-PDT-N018) l (E51-PDTS-N017-2; i E51-PDTS-N018-2) l

2. RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D)

I BRUNS;iICK - UNIT 2 3/4 3-24 Amendment No,

TAdLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TD1E TRIP FUNCTION AND INSTRUMENT Nm1BER RESPONSE TIME (Seconds)#

3. RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) 4 Bus Power Monitor NA (E51-K42 and E51-K43)

5. RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-PS-N011A,B,C,D)

6. RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A,B)

7. RCIC Steam Line Area a Temp - High NA (E51-dTS-N604A,B)

8. Emergency Area Cooler Temperature - High NA (E51-TS-N602A,B)

9. RCIC Equipment Room a Temp - High NA

(E51-dTS-N601A,B) '

5. SilUTDOWN COOLING SYSTEM ISOLATION

a. Reactor Vessel Water Level - Low, Level 1 NA (B21-LT-N01/A-1,3-1,C-1 D-1) _

(B21-LTM-N017A-1,B-1,C-1,D-1)

b. Reactor Steam Dome Pressure - Righ NA s

(B 32-PS-N018A, B)

Radiation monitors are exempt from response time testing. kesponsetimashall be measured from detector output or the input of the t,irst electronic component in the channel. ,

- Isolation actuation instrumentation response time only.

1 Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 -tnd Table 3.6.3.2-1 for valves in eacn valve group so ontain ISOLATIci; ,

SYSTS:t RESPONSE TIME for each valve.

x .. .

s 3RUNStiIC:: - U' LIT 2 3/ '. 3-2 '+A bendment ';o .

f*

1 I

m i{

y :

TABLE 4.1.2-1

$ ISOLATION AgTUATION INSTRUtlENTATION SURVEILLANCE REQUIREMENTS 9

CliANNEL OPERATIONAL CIIANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil

h. TRIP VUNCTION AND INStKUMENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED H

N 1. PRIt!ARY CONT. tin!!ENT ISOLATION

a. Rescroc Vessel Water Level -

1. Low,'Invel 1 (B21-LT-N017A-1 B-1,C-1,D-1) NA(a) NA R(b) 1, 2, 3

( 321 -LTil-N017 A- 1. B- 1, C-1, D-1 ) D M M 1, 2, 3

2. Low, Level 2 (B21-LT-N024A-1,B-1 and t', B 21-LT-N025 A-1, B-1 ) NA(a) NA R(b) 1, 2, 3 c~

u (B21-LT!!-N024A-1,B-1 and B21-LTM-N025A-1,B-1) D M M 1, 2, 3

h. Drywell Pressure - liigh (C72-PT-N002A,B,C,D) NA(8) NA R(b) 1, 2, 3 (C7 2-PT!!-N002 A- 1, B- 1, C- 1, D- 1) D H M 1, 2, 3

c. Main Steam Line

1. Radiation - liigh D W R 1, 2, 3

( D 12-Ril-K603A , B ,C , D)

2. Pressure - Low (B21-PT-N015A,B,C,D) NA(a) NA R(b) g (B21-PTM-N015A-1,B-1,C-1,D-1) D M M 1 Si 3. Flow - liigh

$ (B21-PDT-N006A,B,C,D; NA(a) NA R ID) I k B21-PDT-N007A,B,C,D; g B21-PDT-N008A,B,C,D; l g

. B21-P DT-N009A , B ,C , D)

(B21-PDTM-N006A-1,B-1,C-1,D-1; D M M 1 l B21-PDTM-N007A-1,8-1,C-1,D-1; B21-PDTM-11008A-1,8-1 C-1,D-1; j

B21-PDTM-N009A-1,B-1,C-1,D-1) '

l l

l. _ _ - _ - _ _ - _ _ _ _ _

os

@ TABLE 4.3.2-1 (Continued) d N ISOLATION ACTUATION INSTRilt1ENTATION SURVEILLANCE REQUIREMENTS O

CllANNEL OPERATIONAL g CilANNEL FUNCTIONAL CilANNEL CONDIT10 tis IN WilICil f.; T CilECK TEST g ._Hi e FUNC1'10tl AND INSTRUt1ENT NUl1BER CALIBRATION _SilRVEILLANCE REQUIRED g illARY CONTAINMENT ISOLATION (Continued) -

l

4. Flow - liigh D H M 2, 3 (B21-PDTS-N006A-2; B 21-1'DTS-N0078-2 ;

il21-PDTS-N008C-2; il21-PD rS-fl009 D-2 )

d. !!ain Steam Line Tunnel u Temperature - liigh NA M R 1, 2, 3

) ( B21-TS-fl010A , B ,C, D; u il21 -TS-t101 1 A , B ,C , D ; *

/o B21 -TS-t1012 A , B ,C , D ;

B21-TS-N0134,B,C,D)

e. Condenser Vacuum - Iou (B21-PT-N056A,B,C,D) NA(a) NA R(b) 1, 2#

( B21-PTri-N0 56 A- 1, 8- 1. C- 1, D-1 ) D H H 1, 2#

f. Turbine Building Area Temp-liigh NA M R 1, 2, 3

(!!21-TS- 322 5A , B ,C , D ;

B21-TS-3226A,B,C,D; il21-TS-3227A,B C.D; il21-TS-322BA,B,C,D; g B21-TS-3229A,B,C,D; m il21 -To-32 30A , B ,C , D; ,

h B21-TS-3231A,B,C,D; m B'l-TS-3232A,B,C,D)

?

.U 9'

l

$ TABLE 4.3.2-1 (Continued)

G ,

id y IS01ATION ACTUATION INSTRUf!ENTATION SilRVEILLANCE REQUIREMENTS 9.

, CllANNEL OPERATIONAL

_. CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil '

y TRl_P FUNCTION AND IllSTRUMENT NUtlBER CllECK TEST CALIl! RATION SURVEII.IANCE REQUIRED a

sa 2. SECONDARY CONTAIK!!ENT ISOLATION

a. Reactor Building Exhaust Radiat too - liigh D M R 1,2,3,5, and *

(D12-RM-N010A,B)

h. Dryuell Pressure - liigh (C72-PT-N002A,B,C,D) NA(a) NA R(b) I, 2, 3 (C72-PTft-N002A-1,B-i,C-1 D-1) D H H 1, 2, 3

c. Reactor Vessel Water level -

low , Level 2

{ (B21-LT-N024 A-1,B-1 and NA(a) NA R(b) 1, 2, 3 B21-LT-N025 A-1,B-I) h s (B21- LTM-NO24 A-1,B-1 and D M M 1, 2, 3 B21-LT!!-N025 A-1, B-I)

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - liigh D M R 1, 2, 3 (G31-dFS-N603-1A,1B)

h. Area Temperature - liigh NA M R 1, 2, 3 (G31-TS-N600A,B,C,0,E,F)

c. Area Ventil+ation A Temp - liigh NA H R 1, 2, 3

, (G31-TS-N602A,B,C,D,E,F)

D, g d. SLCS Ini t ia t ion NA R NA 1, 2, 3 g (C41A-SI) h e. Reactor Vessel Water level -

Iow, Ixve l 2 o

(ll21-LT-N024 A-1, B-1 and NA(a) NA R(h) 1, 2, 3 ll21-LT-N025 A-1, B-1)

(B21-LTM-N024 A-1,B-1 and li' M M 1, ? , 3 1121-LT!!-NO25 A-1,B-1) ,

$ TABLE 4.3.2-1 (pontinued)

El I3 ISOLATION ACTUATION INSrRUMENTATION SURVEILLANCE REQUIREMENTS O

, CilANNEL OPERATIONAL CllANNEL FUNCTIONAL CilANNEL CONDITIONS IN 11111C11 QI P FilNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED

,- i sa 4. CORE STANDBY C001,ING SYSTEMS ISOLATION

a. liigh Pressure Coolant Injection System Isolation ,

1. IIPCI Steam Line Flow - liigh (E41-PDT-N004; NA(a) NA R(b) 1, 2, 3 E41-PDT-fl005)

(E41-PUTS-N004-2; D M M 1, 2, 3 E41-PDrS-fl005-2)

2. IIPCI Steam Supply Pressure -

u Low NA M R 1, 2, 3 eb ca (E41-PSL-N001A,B,C,D)

3. IIPCI Steam Line Tunnel Temperature - liigh NA M Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3388; E41-TS-3489)

Ei e 4. Bus Power Monitor NA R NA 1, 2, 3 E. (E41-K55 and E41-K56) u

$ 5. IIPCI Turbine Exhaust

,", Diaphragm Pressure - llagh NA M 1, 2, 3

- Q

( E41 - PSil-N012 A , B ,C , D)

.o

6. IIPCI Steam Line Ambient Temp - liigh IIA H R 1, 2, 3 (E51 -TS-fl603C , D)

TABLE 4.3.2-1 (Continued) if d ISOLATION ACTUATION INSTittIMENTATION SURVEILLANCE REOUIREMENTS O

, CllANNEL OPERATIONAL CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WillCil d TR i t> FtINCTION AND INSTRutlENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED H

's 7. IIPCI Steam Line Area A Temp - liigh NA 11 R 1, 2, 3 (E 51-dTS-N604C , D) '

8. Emergency Area Cooler Temp - liigh NA M Q 1, 2, 3 (E41-TS-N602A,B)

b. Reactor Core Isolation Cooling System Isolation

y. 1. RCIC Steam Line Flow - liigh e (E51-PDT-N017; NA NA R 1, 2, 3 y E51-PDT-N018)

!$ (E51-PDTM-N017-2; D M M 1, 2, 3 E 51-PDT!!-N018-2)

2. RCIC Steam Supply Pressure - Low NA M Q 1, 2, 3 (E51-PS-N019A,B,C,D)

3. RCIC Steam Line Tunnel liigh Temperature NA M R 1, 2, 3 (E51-TS-3319; E51-TS-3320;

, E51-rS-3321; (g E51-TS-3322; E51-TS-3323; (1

E51-TS-3355; g E51-TS-3487)

g 4. Bus Power flonttor NA R NA ,

I , 2, 3 (E51-K42 and E51-K43) -

') . RCIC Turbine Exhaust ,.

Diaphr.sgm Pressure - liigh NA M R 1, 2, 3 (E51-PS-N012A,B,C,D)

e i

en g TABLE 3.3. d3 is N EMERCENCY CORE C001,INC SY_S.T_EM ACTUATION INSTRUMENTATION n - .-

M MINIMUM NUMllER APPLICABLE g OPERAllLE CilANNELS OPERATIONAL M --Trit' FilNCTION AND IslSTRUllENT NUtlBER PER TRIP SYSTEM CONDITIONS ACTION' o

'd

1. CORE SPRAY SYSTEll _---

a. Reactor Vessel Water level - low, lovel 3 2 1, 2, 3, 4, 5 30 .

(!!21-LT-NO31 A , B ,C , D)

(!!21-LTS-NO31 A-4, B-4,C-4, D-4 )

h. Reactor Steam lbme Pressure - Low (Injection Permissive) 2 1,2,3,4,5 31 (ll21-PT-N02 l A , B ,C , D)

(B21-PTS-N021A-2,B-2,C-2,D-2) w c. Drywell Pressure - liigh 2 1, 2, 3 30

) (E l t.-PT-N0 l l A , B ,C , D) u (El 1-PTS-Il011 A-2, B-2,C-2, D-2)

I

$ d. Time IMlay Relay 1 1, 2, 3, 4, 5 31 (E21-K16A,B)

e. lius Power :lonitor# 1/ bus 1,2,3,4,5 32 (E21-KI A ,Is)

2. L0tl PRESSURE COOLANT INJECTION MODE OF RilR SYSTEM l

a. Drywell Pressure - Illgh 2 1, 2, 3 30 (El1-PT-N01IA,B,C,D)

(El 1-PTM-fl011 A-1, B-1,C-1,D-1)

., b. Reactor Vessel Water Level - Iow, Level 3 2 1, 2, 3, 4*, 5* 30 h (B21-LT-NO31A,B,C,D) 1 ( B 21-LTS-NO31 A-4, B-4,C-4, D-4) u y c. Reactor Vessel Shroud Invel (Drywell Spray Permissive) 1 1, 2, 3, 4*, 5* 31

(!!21-LT-NO36 and il21-LT-NO37) y (B21-LTM-NO36-1 and il21-LTM-NO37-1)

.l . Reactor Steam Ik>me Pressure - Iow (Injection Permissive)

(B21-PT-N02iA,B,C,D) ..

(B21-PT:1-NO2lA-1,B-I,C-I,D-1)

( B 21 -PTS- NO21 A-2,11-2, C-2,1)-2 )

1. HilR 1% p Start and I.PCI Injection Valve Actuation 2 1, 2, 3, 4*, 5* -31

2. Recirculation loop Pump Discharge Valve Actuation 2 1, 2, 3, 4*, 5* 31

TAILLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION n

, MINIl1UM NUMBER APPLICABLE OPERABLE CilANNELS OPERATIONAL "j

TRIP FUNCTION AND INSTRU!!ENT NUMBER PER TRIP SYSTEM CONDITIONS ACTf0N H

u LOW PRESStlRE COOLANT IrlJECTI0tl !! ODE OF RilR SYSTEM (Continued) l

e. RilR Pump Start - Time Delay Relay 1 1, 2, 3, 4*, 5* 31 (STR-2Al.2 and STR-2BI,2)

f. Bus Power !!onitori 1/ bus 1, 2, 3, 4*, 5* 32

,(El1-K106A,B) u 3. 111C11 PRESSURE COOLANT INJECTION SYSTEM l

N a. Reactor Vessel Water level - low, Level 2 2 1, 2, 3 30 y ( B21-LT-NO31 A ,ll,C, D) pj (B21-LTS-NO31A-2,B-2,C-2,D-2)

b. Drywell Pressure - Iligh 2 1, 2, 3 30 (El1-PT-N01IA,B,C,D)

(EIl-PTS-NotIA-2,B-2,C-2,D-2)

c. Condensate Storage Tank Imvel - Iow 2** 1, 2, 3 33 (E41-LS-Il002, E41-LS-N003)

d. Suppression Chamber Water Imvel - Iligh 2** 1, 2, 3 33 (E41-LS!!-N015A,B)

e. Bus Power >fonitor# 1/ bus 1, 2, 3 32 g (E41-K55 and E41-K56)

E Q 4. AllTotIATIC DEPRESSURIZATION SYSTEM l

h a. Drywell Pressure - liigh, coincident with 2 1, 2, 3 30

., (E I l-PT-Il010A , B , C , D)

,'o' (El1-PTM-N310A-1,B-1,C-1,D-1)

b. Reactor vessel Water level - Iow, ' Level 3 2 1, 2, 3 30

( 821 -LT-NO 31 A , B ,C. D)

(B21-LTS-NO31A-3,B-3,C-3,D-3)

w y TABLE 3.3.3-1 (Continued) ii N EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION n -

MINIMUti NUMBER APPLICABLE

,; OPERABLE CilANNELS OPERATIONAL i gl* FilflCTION AND IriSTRUMEtif NUllBER PER TRIP SYSTEM CONDITIONS _

ACTION A_UTo!!ATIC DEPRESSURIZATION SYSTEM (Continued) l

c. Reactor Vessel Water Level - Iow, level 1 i 1, 2, 3 30

( B21 -LT-fl042 A , B)

( B 21-LTM-fl04 2 A- 1, B- 1 )

d. ADS Timer 1 1, 2, 3 31 (B21-TDPU-KSA,B)

e. Core Spray Poinp Discharge Pressure - liigh (Permissive) 2 1, 2, 3 31 (E21-PS-N008A,B and E21-PS-N009A,B)

f. RiiR (LPCI MODE) Pump Discharge Pressure - liigh (Permissive) 2/ pump 1, 2, 3 31 T' (Ell-PS-N016A,B,C,D and

,$ Ell-PS-N020A,B,C,D)

g. Bus Power !!onitor# 1/ bus 1, 2, 3 32 (B21-KIA,B)

APPLICABLE TOTAL NO. CllANNELS MINIMUM CllANNELS OPERATIONAL FUNCTIOilAl. UNIT OF CilANNELS TO TRIP OPERABLE CONDITIONS ACTION

5. LOSS OF POWER l p a. 4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4##,5## 34 d IIndervoitage (loss of Voltage) fj b. 4.16 kv Eme rgency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4##,5## 35 lladervoltag2 ( Deg raded y Voltage)

No t applicable when two core spray system subsytems s are OPERABLE per Specification 3.5.3.1.

2* Per,vides signal to UPCI pump suction valves only.

Alarm only.

//# (Uquired when ESF equipment is required to be OPERABLE.

nn

TABLE 3.3.3-2 en

$ EMERGENCY CORE COOLING SYSTEH ACTUATION INSTRUMENTATION SETPOINTS G!

ALLOWABLE PRII,* flRJCTION AND INSTRUMENT NUMBER VALUE TRQ*SETPOINT s

'8

1. CHRE SPRAY SYSTEll IJ

a. Reactor Vessel Water Imvel - Iow, Icvel 3 > + 2.5 inches * > + 2.5 inches *

(B21-LTS-NO31A-4,B-4,C-4,D-4)

b. Reactor Steam Ibme Pressure - Iow 410 + 15 psig 410 + 15 psig (ll21-PTS-N021 A-2, B-2,C-2,D-2)

c. Drywell Pressure - Iligh -< 2 psig -< 2 psig (EIl-PTS-Nol1A-2,B-2,C-2,D-2)

d. Time Delay-Relay 14 < t < 16 secs 14 < t < 16 secs

" (E21-K164,B) o y e. Ilus Pawer Monitor NA NA 6r (E21-KlA,B) ,

2. Loll PRESSURE COOLANT INJECTION HODE OF RilR SYSTEr4 l

a. Drywell Pressure - liigh < 2 psig < 2 psig (E l l-PT!I-N01'I A- 1, B- 1, C- 1, D- 1 )

h. Reactor Vessel Water Level Iow, level 3 > + 2.5 inches * > + 2.5 inches *

(B21-LTS-N011A-4,B-4,C-4,D-4)

c. Reactor Vessel Shroud level -

> - 53 inches * > - 53 inches *

(B21-LTM-NO36-1 and -

B21-LT!!-fl03 7-1 )

h. al . Reactor Steam Ibme Pressure - Low is Q l. RilR Pump Start and LCPI Valve g Actuation 410 + 15 psig 410 + 15 psig r'

(B21-PTS-NO21A-2,B-2,C-2,D-2) _

f 2. Recirculation Pump Discharge Valve Actuation 310 t 15 psig 310 i 15 psig (Il21-PT:1-N021 A- 1, B- 1, C- 1, D-1 ) ..

3 8LE 3.3.3-2 (Continued) lii EMERGENCY CORE COOLING SYSTEM ACTUATIOf1 INSTRUMENTATION SETPOINTS P:

ALLOWABLE

,g p IP FUNCTION AND INSTRUMENT NUMBER TRIP SETPolNT VALUE M

1.oW PRESSURE COOLANT IN.IECTION MODE OF RRR SYSTEM (Continued) l

e. HilR Pump Start - Time Delay Relay 9<t <- 11 seconds

-- 9<t<- 11 seconds l (STR-2Al.2 and STR-2Bl.2)

f. Isus Power tionitor NA NA (Ei1-K106A,B)

3. lilGli PRESSURE C001. ANT INJECTION SYSTEM l

u a. Reactor Vessel Water Level - Iow, Imvel 2 > + 112 inches * > + 112 inches

D (B21-LTS-NO31 A-2, B-2,C-2,11-2)

I'

b. Drywell Pressure - liigh -< 2 psig -< 2 psig (EIl-PTS-Nol1A-2,B-2,C-2,D-2)

c. Condensate Storage Tank Imvel - Low > 23 feet 4 inches > 23 feet 4 inches (E41-LS-fl002; E41-LS-t1003)

1. Suppression Chamber Water Level - liigh < -2 feet ** < -2 feet **

( E41-LSil-!1015A , B)

e. Bus Power :lonitor NA NA (E41-K55 and E41-K56)

4. AUTollATIC DEPRESSURi?.ATION SYSTEM f

a. Drywell Pressure-liigh < 2 psig < 2 psig n ( E l l-PTri-N010 A- 1, B- 1, C-l > D- 1 )

s

$- t2 Reactor vessel Water level - Low, level 3 > + 2.5 inches * > + 2.5 inches

y (ll21-IlfS-NO31 A 's, B-3,C-3,D-3) o a c. Reactor Vouse t Water level - Iou, Level I > + 162.5 inches *

> + 162.5 inches *

, (Is21-LTri-H042 A- 1, B-1)

.l . ADS Timer (li21-TDPU-KSA , B) < 120 seconds < 120 seconds

us p

.2 --TABLE 3.3.3-2 (Continued)

Ed

j EMERGENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION SETPOINTS O.

, ALLOUABLE

.l.H..I.P.._F_UtiCT_ ION AND INSTRUMENT NUMBER _T_R_IP SETPOINT VALUE s

AUTullATIC DEPRESSURIZATION SYSTEM (Continued) l

e. Core Spray Pump Discharge Pressure - liigh > 100 psig > 100 psig ,

(E21-PS-N008A,B and E2l-PS-N009A,B)

f. RilR (LPCI MODE) Pump Discharge Pressure - liigh > 100 psig > 100 psig (Ell-PS-N016A,B,C,D and E l 1-PS-N020A , B , C , D)

g. lius Power Monitor NA NA g (B21-KIA,B)

5. LOSS OF POWER

a. 4.16 kv Emergency Bus Undervoltage a. 4.16 kv Basis - 2940 i 161 volts 2940 i 315 volts (Loss of Voltage)# b. 120 v Basis - 84 i 4.6 volts 84 i 9 volts

c. < 10 sec. time delay < 10 sec. time delay

b. 4.16 kv Emergency Bus Undervoltage a. 4.16 kv Basis - 3727 i 9 volts 3727 t 21 volts (Degraded Voltage) b. 120 v Basis - 106.5 i 0.25 volts 106.5 i 0.60 volts

c. 10 1 0.5 sec. time delay 10 i 1.0 sec. time delay N

5 B

n y

This is an inverse time delay voltage relay. The voltages shown are the maximum that will not result In a trip. Lower voltage conditions will recult in decreased trip times.

Vessel water levels refer to REFERENCE LEVEL ZERO.

- Suppression chamber' water level zero is the toru's centerline minus 1 inch.

ta -

y TABLE 4.3.3-1 Li

$ EMERGENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION SllRVEILLANCE REQUIREMENTS O

CllAtlNEL OPERATIONAL g CilANNEL FilNCTIONAL CilANNEL CONDITIONS IN WilICll y TRI8 FullCTION AND IllSTRUMENT NUMBER CIIECK TEST CALIBRATION SURVEILLANCE REQUIRED a

'J

1. CORE SPRAY SYSTEtt

a. Reactor Vessel Water level - .

i Iow , Level 3

( B21-I.T-NO 31 A , B ,C , D) NA(a) NA R(b) 1,2,3,4,5 (B21-LTS-NO31A-4,B-4,C-4,D-4) D M M 1,2,3,4,5

h. Reactor Steain Dome Pressure - low (B21-PT-N021A,B,C;D) NA(d ) NA R(b) 1,2,3,4,5 (B21-PTS-N021 A-2,, B-2,C-2, D-2) D M M 1,2,3,4,5

c. Drywell Pressure - liigh

[ (Ell-PT-N0llA,B,C,D) NA(a) NA R(b) 1, 2, 3 (Ell-PTS-N0llA-2,B-2,C-2,D-2) D M M 1, 2, 3-

d. Time Delay Relay NA R R 1,2,3,4,5

( E21'-K l 6A , B)

e. has Power Monitor NA R NA 1, 2, 3,4,5 (E21-KlA,B)

2. Uni PRESSURE COOLANT INJECTION MODE OF RilR SYSTEM l

a. Drywell Pressure - High (Ell-PT-N0llA,B,C,D) NA(a) NA R(b) 1, 2, 3 (Ell-PTri-NollA-1,B-1,C-1,D-1) D M' M 1, 2, 3 g h. Reactor Vessel llater level -

Iow, Level 3 h (B21-LT-NO31A,B,C,D) NA(3) NA R(b) I, 2, 3, 4*, 5*

@ ( H21-1.TS-NO31 A-4,B-4,C-4,D-4) D M M- 1, 2, 3, 4*, 5*

, c. Re.sctor Vessel Shroud level

, ,E (B21-LT-NO36 and B21-LT-NO37) NA(a) NA R(h) I, 2, 3, 4*, 5*

(B21-LTM-NO36-1 anil B21-LTM-NO37-1) D M M 1, 2, 3, 4*, 5*

e

TABLE 4.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS a

CtlANNEL OPERATIONAL

[, CllANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil y, TRie FUNCfl0N AND INSTRUMENT NUMBER CilECK TEST CALIllRATION SURVEILI.ANCE REQUIRED on o I.0tl PRESSllRE COOLANT INJECTION MODE OF RilR SYSTEM (Continued) l

d. Reactor Steam Dorac Pressure - Iow NA(a) NA R(b) 1, 2, 3, 4*, 5*

(821-PT-N021A,B,C,D)

1. RilR Pump Start and LPCI Injection Valve Actuation D M M 1, 2, 3, 4*, 5*

(1121-PTS--N021 A-2, B-2,C-2, D-2)

2. Recirculation Inop Pump Discharge Valve Actuation D M M 1, 2, 3, 4*, 5*

{ (H21-PTM-N021A-l.B-1,C-1,D-1) u e. RilR Purnp Start - Time Delay Relay NA R R 1, 2, 3, 4*, 5*

g (STR-2Al,2 and STR-2B1,2)

f. lius Power Monitor NA R NA 1, 2, 3, 4*, 5*

(Ell-K106A,B) 3.111C11 PRESSURE C00LANT INJECTION SYSTEM l

a. Reactor Vessel Water level -

Inw , Level 2 (821-LT-NO31 A,II,C , D) NA(a) NA R(b) 1, 2, 3 (B21-LTS-NO31A-2,B-2,C-2,D-2) D M M 1, 2, 3 N h. Drywell Pressure - liigh N (El1-PT-N01IA,B,C,D) HA(a) NA R(b) 1, 2, 3

{$i (El1-PTS-N011A-2,B-2,C-2,D-2) D M M 1, 2, 3

c. Condensate Stcrage Tank level - Iow NA M Q 1, 2, 3 g (E41-LS-N002; E41-LS-N003) 11 . Suppression Chamber Water Icvel - liigh NA M Q 1, 2, 3

( E41 -1.Sil-NO 15A , B) ..

e, lios Power Monitor NA R NA 1, 2, 3 (E41-K55 and E41-K56)

TABLE 4.3.3-1 (Continued) ils

$ EMERCENCY CORE COOLING SYSTEtt ACTUATION INSTRilHENTATION SURVEILLANCE REQllIREMENTS il

, CilANNEL OPERATIONAL

c. CllANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil f'j TRIP FilNCTION AND INSTRUMENT NUHiiEP. CllECK TEST CALIBRATION

.- i SilRVEILI.ANCE REQUIRED

'J

4. AUTOfiqIC DEPRESSURIZATION SYSTEM l

a. Dryuell Pressure - liigh *

( E l l-PT-N010 A , li , C , D) NA(a) NA R ID) 1, 2, 3 (E 11-PT!i-N010 A- 1, B- 1, C- 1, D-1 ) D H H 1, 2, 3

h. Reactor Vessel Water level -

Iow, level 3 (B21-LT-NO31A,B,C,D) NA(a) NA R(b) 1, 2, 3 (ll21-LTS-NO31 A-3, B-3,C-3,D-3) D H H 1, 2, 3

c. Reactor Vessel Water level -

Inu, level 1 (B21-LT-N042A,B) NA(a) NA ~R(b) 1, 2, 3 y (B21-LTM-N042A-1,B-1) D H H 1, 2, 3

d. ADS Timer NA R R 1, 2, 3 (B21-TDPU-KSA,B)

e. Core Spray Pump Discharge Pressure - liigh NA H Q 1, 2, 3 (E21-PS-N006A,B and E21-PS-N009A,B)

t. Ki!R (LPCI H01)E) Pump Discharge Pressure - llidh NA H Q 1, 2, 3 g (Ell-PS-N016A,B,C,D and g El1-PS-N020A,B,C,D) k g. isus Power Monitor NA R NA 1, 2, 3 g (il21-KI A ,15)

>l

,'

ML20083M831

Text

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