Text

Tech Specs Tables 2.2.1-1,3.3.1-1,3.3.1-2,4.3.1-1,3.3.2-1, 3.3.2-2,3.3.2-3,4.3.2-1,3.3.3-1,3.3.3-2,4.3.3-1,3.3.5.3-1, 4.3.5.3-1,3.3.6.1-1,3.3.6.1-2,4.3.6.1-1,for Unit 1 & 3.3.3-1,3.3.3-2 & 4.3.3-1 for Unit 2
	ML20004F563
Person / Time
Site:	Brunswick
Issue date:	06/11/1981
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20004F561	List: ML20004F560; ML20004F563;
References
	NUDOCS 8106190084
	Download: ML20004F563 (48)
	v • d • e

.

CO W

O ,

CB C

TABLE 2.2.13 o

REACTOR PR(T ECI'lOtl SYSTDI INSTRllHEITTATinti SETroitTIS

@g g I)

C p AI.lAMAltlE d Filt3CTlotMI. UNIT AllD INSTRllflENT NUllHER TRIP SETPollff VAIJfES 1, Intermediate Range Monitor, Neutron Flux - liigt I $120 divisions of full scale <l20 divinlinii p (C51-IRH-K601 A, B,C,D,E,F.C.II) of fiell acalc Il

2. Average l'ower Range Monitor (C51-A PRH-Cll . A . B .C. D. E, F)

a. Neutron Flux - liigli, 157. <l57. of RATED TilERtMI. POWER < l57. of HATEli TilEktlA I.114f ER -

Is . Flow Blased Heutron Flinx - liigl: I3)( ') 3(0.66 W F 547.) 1(0.66 W I 547.)

c. Fixed Neutron Flux - liigt: I#') 31207. of RATED 11tEHthl. PIMER $1207, of PA1ED TilElunt. P(UEH Tt~

3. Itcactor Vessel Steam Dome Pressure - liigli

( 1121-ITH-IIO 23A- 1, B-1, C- 1, D-1) 11045 psIg 11045 pair,

4. Ilenctor Vessel Water f.evel - Iow, i. eve l >+162.5 inclien nliove top

( B21- LTil-H017A-1, B- 1, C- 1, D- 1 )

>t162. ' Incli. n above fuel guide t op lin 1 nu lite P

5. Main Steam 1.ine isolation Valve - Closore(5) <107. closed sill 7. closed (B21-F022 A,B,C,D; B21-F028 A,B,C,D) g.

,E, 6 Main Steam 1.ine Radiation - liigli 53 x full power bnckground <3.5 x Inli pous a

- (D12-RM-K603 A,B,C,D) lea cl<gi enind N

i G

4

^

=

1 -

TABIE 2.2.1-1 (continued)

_RMCTOR PROTECTION SYSTEtl INSTRUMElfrATION SETIUltirS h AI.l AMA HIE l* FiftWJrIONAI. UNIT AND INSTRilHEfff NIIHRER TRI? SETP0lfir VAIJIES

7. Drywell Pressure - Illgli 9 (C71-PS-lH)02 A ,B,C,0) [2 pata 17.sta 1

1

8. Scrama Discharge Volunic Water Level - liigh 1109 gallons $109 gallons (Cil-LSil-N013 A ,B,C,D)

9. Turbine Stop Valve - Closure (6) < 10% closed < 10% closed (EllC-SV05-IX 2X 3X,4X) m 10. Turbine Control Valve Iast

' ControlOilPressure-Low (g}osure. * > 500 psl9

_ -> 500 psig

([IlC-PSL-1756,1757,1758,1759)

1

/,

.s

TABl.E 3.3.1-1 REACTOR PROTELTION SYSTEH INSTRtitENTATIOff N APPI.lCAnt.E filfilfluff NtitlRFR N OPERATIONAI. OPERARI.E CilArillEl.S N

g FlHCTIONAL UNIT AND INSTRtitEffr NUHRER CONDITIONS PER TRIP SYS1Eff(al(IQ AtritM4 M

1. Intermediate Range Monitors:

(C51 - I RM-K601 A, B , C, D, E , F. C. II) 9 A

+5 a. Heutron Flux - Illgh 2,5(b) 3 1 3, 4 2 2

h. Inope ra t ive 2, S 1 1 1, 4 2 2

2. Average Power Range Honitor:

(C51 - APRH-Cll. A . II. C. D.E . F. )

a. Neut ron Flux - liigli, 157, 2, 5 2 3 y In . Flow Blased Neutron Flux - liigh 1 2 4 e Fixed Neut ron Flux-Illgli, 1207.

c. I 2 4 9 d. Inope ra t ive I, 2, 5 2 5 L e. Downscale 1 2 4 LPRH

f. 1, 2, 5 (c) NA j 3. Reactor vessel Stenis Dome Pressure -

liigh

( il21 -PT-H02 3 A , B , C, D)

(Il21-PTH-N02]A-1,5-1 C-1,D-1) 1, 2(d) 2 6

4. Reactor Vessel ifater Level Low, I.evel #1

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

, ( H 21 -I.TH-N017 A- 1, R-1. C- 1, D- 1 ) 1, 2 2 (i n.

I 5. flain Steam Line Isolation Valve -

E. Closure (B21-F022A,B,C,D, and y ll21 - F028 A, n , C , D) 1 4 4

TABI.E 3.3.1-1 (Continued),

en REACTOR PR(YTECTION SYSTEM IllSTRitF.NTATION APPI,1CARI.E HINIHlit! 13tilfilER

[q1 OPERATI(NAI. OPERAlti,E CllANNdl.S Q FUNCT IONAL UNIT AND INSTRUMERP NielBER C(NDITIONS PER TRIP SYSTEll(a)(la), At T i ott

6. Hain Steam I.ine Radiation - liigli I, 2( } 2 /

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

~

7. Drywell Pressure - liigli (C71-PS-N002 A,9,C,0) (e)

8. Scram Discliarge Volume Water 1.evel -

liigli (Cll-1. Sit-N013A,B,C, D) 1, 2, 5 II} 2 5 u 9. Turbine Stop Valve - Closure 1(8 4 8

) ( EllC-SVOS-I X,2X,3 X,4 X) y 10 Turlitne Control Valve Fast Closure

" 1(g)

Cont rol Oil Pressure - 1.ow 2 8

( EllC-PSL-17 56,1157,1758,1759

11. Reactor Mode Switcle in Sliutdown 1,2,3,4,5 1 9 Position (C11A-SI)

12. llanual Scrani (C71 A-S3A,5) 1,2,3,4,5 1 10 2

F

TABIE. 3. 3.1-2 l

, REAcr0R PRUIECTION SYSTEM RESPONSE tiles su FIR 4Crl0NAI. tRitT AND INSTRINENT HilHRER RESPONSE TifE_(Secunals )

N Q l. Interinedtate Range Monitora (C 51-I RM-K601 A , B , C, D,E . F. C. II) :

e

s. Neutron Flux - Ilighe 11A h, b. Inoperative flA e

2. Ave rage Poue r Rasige Monitor * (CSI-APRH-Cll. A, B,C,D,E,F):

a. Neutron Flux - litgh,157.

10.09

h. Flow Blased Neutron Flux - liigh NA

c. Neutron Flux - Nigh, 1207.

d. Inoperative 10.09 NA

e. Downscale NA

f. LPRH HA Zs' 3. Reactor Vessel Steams Dome Pressure - liigh v (B21-PT-N023A,B,C,D) <0.55

& (n21-PTH-N023A-1,8-1,C-1 D-1)

4. Reactor Vessel Water Level - Level #1

( R21-LT-N017A-1, B-1, C-1,1)-1) 11.05 (B21-LTH-N017A-1,R-1,C-1,D-1)

5. Main Stease Line Isolation Valve-Closure (R21-F022A,R,C,D an<l H21-F028A,B,C,D) 10.06 6 Haf n Steam Line Radiation - litgh (D12-RH-K603A,B,C,D) NA

7. Drywell Pressure - Illgh E. (C71-PS-N002A,8,C,0) "^

R

s

8. Scrani Discharge Volunee Water Level - liigli (Cll-LSN-H013A,it,C,D) IIA Y

9 Turleiue Stop Valve - Closure (EllC-SVOS-l X. 2 X,3 X.4 X)

$0.06

4

)

s d

n o

c e

S

(

m E

l o

r i 8 f T 0 l

e E 0 A A c S

1 < l t

t I r t u i s I' n S e E m R_

e i

l i

t n

la s

o m

i S t E

i e .

nl T ne

) E um pa d S s n e i t

eh u 0 ) R r n P 9 i S 5 n t E 7 .i n R 1 g o ,

nt C t t 8 ) i n

( E 5 1 t e T 7 S s n S 1 - eo 2 Y ,

A t p

- S 7 1 m

1 5 7 eo 3

. N O

7 1 (

C i

mc

. I ,

t c 3 T 6 n i C 5 o en E. E 7 i s o f

I R U 1 t i

nr A R . ot

,I s pc T P eS o s e rP P el R R u - r e O E sC n T 1 1 oH w mt C H l E o on A U C( d r r E N t f i R t w u f T n o, h ) t N a1 S 5, pf F n o E - n A s

e U e i 3 xt R ve S eup T l r h -

S au c A en H V s t 1 ri

- 1 s i 7 a l e w C r D oa S ( n o N rP r

_ A t e i n ot n1 d a t u

_ T o1 o r cp C0 M

_ I c et

_ N S t u

_ U el r eo no o l d

I, 1 r t a r A t: t c u no N r n a n ot 0 uo e a r c 1 TC R M t e 7, ut M . . .

c e ff 0 1 id t

i 2 F 1 1 1 E

wsP h :ss e p , E 4, ~ U s- Y o, > I laia tn y-l

!i!lIll :

O TABLE 4.3.1-1 tn -

f.' REAC1DR <*')TECT10'l SYSTEtt INSTRUMENTATIO!! Si!RVEILLAllCE REQUlHillEllip_

54 h CilA'INEL Ol'ERATIOllAI.

p FilNCTIONAL UNIT CilANNEL FUtlCT10NAl. CilAlltlEl. l'ONulTIOllS IN WillCil AND INSTRUtlEdT NUMBER CllECK g)

, TEST CALIBRATl_Off SURVEll.LAtiCE REfERED h 1. Intermediate Range Honitors:

+1 (C51-IRH-K601 A,B,C,D E F,G,II)

a. Neutron Flux - Illgh D S/UII')IC) R 2 D W R 3,4,5

b. Inoperative NA W NA 2,3,4,5

2. Average Power Range Honitor:

(C51 - APRfl-CII . A, H , C, D, E, F)

a. Neutron Flux - Illgli 157.

S S/UII'), W(d) Q 2 S W Q 5 v li . Flow Blased Neutron Flux-liigh S S/IM),W W (*)II),Q l 2 c. Fixed Neutroni Flux - liigh, u

1207. S S/U ,W W ,y 1

-, d. Inoperative flA W NA 1, 2, 5

e. IA>wnscale NA W NA I

f. l.PRM D NA (g) I , 2, 5

3. Reactor Vessel Steam ikime Pressure - liigh (H21-PT-N023A, B, C, D) NA(h) IIA R(I)

(H21 -P'IM-NO23A-1, R-1, C-l , D-1) D !! H I, 2

$ 4. Reactor Vessel Water I.evel - 1.ow

$ l.evel #1 (n21-1.T-N017A-1, B-1, C-1, D-1) NA NA R(1)

(ll21-til11-N017A-1, R-1, C-1, D-1) D H H I,2 E

5. Ilain St'am 1.Ino Isolation Valve -

Closure (H21-F022 A,B,C.D anil in 11 R(I') y ll21-F028 A,n,C,D) 1

TARI.E 4. 3.1-l__(continued),

5

!j JtEACTUR PROTECTION SYSTEM INS 11tutIEllTATION SLIRVEILI.AllCE REQUIR12tElOS U

'd CllANNEl. OPEPATipt1 AI.

FtINCTIONAL llNIT CilANNEl. FUNCTIONAL CilANNEL CONDITIONS IN Willt:Il AND INS 11tUHEllT NUHilER CilECK_ TEST CAI.lnRAT10tl ") SURVEll.I.ArglLlu;qtil Hl:D G

h 6. Main Steam Line Radiation-!!!gli S M(I) RU) I, 2 (D12-RH-K603 A.B.C.D)

7. Drywell Pressure - liigh (C71-PS-fl002 A,B,C,D) ilA M .

Q l 2 fl . Scrain Discharge Volume Water I.evel - liigh NA Q R 1, 7, 5 (Cil-l.Sil-N013 A, B, C, D) t 9. Turbine Stop Valve - Closure NA !! R(h) y

$ ( EllC-SVOS - t K , 2X, 3X, 4K) 10 Turbine Control Valve Fast Closure, Control Oil Pressure-

, Low (EllC-PSI.-l 756,1757,1758, NA H R I 1759)

11. Reactor Mode Switch in Shutdown HA R NA 1,2,3,4,5 Position (C71A-SL)

12. Hansal Scrum NA Q NA 1, 2, 3, 4, 5

$ (C71A-S3A,5)

$ a. Neutton detectors mte he excluded f rom CilAtlNEl. CAI.I DHATiott.

If h. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to startup, if not perfonned wi ttiin the prevlona 7 days.

E c.

" The IRH channels shall he compared to the APRH cliannels and the SitH insteuments Inr overlap duilng; cach startup, if not perfunned within the previous 7 days.

,$ d. When changing f rom CollDITION 1 to CotIDITlott 2, perfonn the reilut real nin velliance ut ililn 12 hones after entering CotIDITIOtt 2.

e. 1his calthration shall canalst of the ad justment of t he Aritti readout to couloem to the power valuen caletalat ed by a heat balance diaring CollDIT10tl I when TilEltflAL POWElt 2 257. of itATEH *lNEHilAI. PinlElt.

n .

n o e s li -

e m n t e h l n i w i n n g o n n c i o s t o u t t i

)1 s ts 1 o i t p B l F I

l' o E e l p ( s E t o l

i e h h F n t t .

R n k t d o f c i

t j

e m o e .

s h Ff a r n c R i e o b w i l E o t e w p a n lC t o u n A. l l t a .

1 f l c h n 1

t u a c o

) 1 t f i d E R d t t e V P e n i a u R A v a n r n U i u b i S e t n i t h c o p l n N t e i . i a o O f t e r c c I f f c c t

( T o e e r l A p u e e 1 T t r s o h n

- N n e n s t n 1 E e p i . a

. lt m t e y . h 3 U t e l n c bd c

. R s c a e r e 4 T u n c r u d r y S j o i r o l E. N d s u s ie i. p l i

l 1 a t y c f s t B s h n s e n A t i e a p d o i r o T T. h e r i t m

. I t l a a t at %

S' d a s o e Y f t f n i n h S o a o a d s t t a i s N t d t s r i m O s e s k o I i t i a d ck r T s a s r ec f C n r n g a h e E o b o n d ch d T c i c i n c e O . l s a l t R l l a l u t er p P l a c l s ne m an a t nt e R h g e h n a at x U si b s e hi e I

C' n s

l n m

n g

n cms e A

E ow i o l

a i o

i g i s

rn ea r

a R tl h t l u t r af s a a t t s r , r n i r bd s me b t o me e i e i n i st t l t aa

'H R s t l a

e m

t a

na ar i t

cr P y c u r r a m h L s r b t p s st s t i e n -

il eP i s l es a -

ha hI h n a h r

't c TT T I C TA T -

f g h 1 .J k I En$w9'Njr

!i

[ T Y T t t 3 ,, .

v.

TACLE 3.3.2-1 ISOLATION ACTUATION INSTRUIENTATION VALVE CROUI'S HINIMIRI IllIHRER Al'i'I.I CA nl.E U OPERATED BY Ol'ERABLE CilANNEI.S Ol*l:ltATIOtlAl.

N TRIP FUNCTitti AND INSTRUMENT HIIHRER SIGNAL (a) CollDITIoll x PER TRIP SYS1EH(l>)(c) Attrioll

l. PRIMARY CONTAINHENT ISOI.ATION f}

U a. Reactor Vessel Water Level - Low w

1. Level #1

( B21-LT-H017 A- 1, B-1, C-1, D-1)

(B21-LTH-H017A-1,8-1,C-1,D-1) 2, 6, 7, 8 2 1, 2, 1 20

2. Level #2 (B21-LT-H024A-1,B-1,and 821 LT-N025A-1,B-1 w (B21-LTil-N024A-l,B-1 and

) B21-l.TH- t1025 A-1 B-1) 1, 3 2 1, 2, 3 20 Y

l> . Drywell Pressure - liigli (C71 -l'S-il002 A .0,C .0) 2,6,7 2 1, 2, 1 20

c. Main Steam 1.Ine

1. Radiation - liigli (d) 1 2 1, 2, 3 21 (DI2-RM-K603A,B,C,D) i

2. Pressure - I.ow a (1121 -l'S-1101 S A ,Il,C .0)

E 1 2 I 22 R

l,'

o TABIE 3. 3. 2-1 (Continued)

, ISOLATI0tl ACTUATION INSTRIRENTATION

ss 13 VAI.VE CROUPS HINItHitt HUtlBER ' APPL.II:AniF.

U: OPERATED BY OPERARIE. CllANNEI.S OPEll ATit WAl.

}'

TRIP FUNCTION AND INSTRUtEffr HUMBER SIGNAL (a) PER TRIP SYS1 Ell (Is)(c) Ot tHill Ti t sti ACTitxl I. PRIHARY CottrAlteEttr IS01ATIfM (Continued)

N Il c. liain Steam 1.ine (Continued)

3. Flow - liigh 1 2/1ine 1 22 (B21 -dPIS-11006 A ,0,C ,0; D21-dPIS-11007 A ,8,C ,D ; U21-dPIS-11008 A ,B ,C .0 ; and U21 -dPIS-it009 A ,B ,C .0) t e

Y

~

d. Main Steam Line Tunnel Temperature - High 1 2(e) I , 2, 1 21 (B21-TS-N010A,8,C.D; B21-TS-H011 A,B,C,D; B21-TS-H012A,B,C,D and B21-TS-H011A,8,C,D)

e. Condense r Vacuum - low (H21-PS-fl056 A.B,C,0) 1 2 1, 2(f) 21 l

f. Tu ris t ne Building Area Temperature - liigh I le(e) I , 2, 1 21 g (R21-TS-32254,B,C,D; il21-TS-3226A,B,C,D; n21-TS-1227A,B,C,D; R21 -TS-3 2 2 fl A , n , C, 0; a

B21-TS-3229A,B,C,D; B21-TS-3230A,n,C,D; n21-TS-3231A,B C.D; and H21-TS- 3232 A,R,C,D) a.

it

.E

TABI.E 3.3.2-1 (Continuest)

ISOLATI(R1 ACTUATION INSTRUtENTATION 73 VALVE CROUPS HINIHlt! HIRIBER APPL.lCAltl.E Q OPERATED BY OPERARI.E CilAtillEl.S OPER AT i t tl Al.

TRIP FUNCTION AND INSTRtRElfr NUMBER SICHAL(a) I'ER TRIP SYSTEM (la)(c) CON DITl ot{ , ACT i t ti

2. SECONDARY CONTAINHENT ISOLATION

.) a. Reactor Building Exhaust

, Radiation - High 6 1 1, 2, 1, 5 and

21 g ( D12-RH-N010 A, B)

b. Drywell Pressure - liigh (C71-PS-N002 A,B,C,0) 2, 6, 7 2 1, 2, ) 25

c. Reactor Vessel Water Level - 1.ow, Level #2 (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1) v ( B21-L'111-t1024 A-1, B-1 and

!!21 - LTH-il02 5 A- 1, B-1 ) I, 3 2 1, 2, 3 21

3. REACTOR WATER Cl.EANifP SYSTEM IS01,ATION

a. A Flow - liigh 3 1, 2, 1 3 24 (C31-dFS-H60 3-I A,l n)

h. Area Teniperature - liigh 3 2 1, 2, 1 24 (C31-TS-N600 A . R .C . D. E , F)

c. Area Ventilation A Temp. - High 3 2 1, 2, 3 24

{u d.

( C31 -TS-N602 A, B , C, D, E , F)

St.CS Initiation (C41A-SI) 3(g) NA 1, 2, 3 24 A-

c. Reactor Vessel Water I.evel -

I.ow , Level #2 (B21-I.T-N024A-1,H-1 and

}g H21 -1.T-N0 2 5 A-1, R- 1 )

( n21 -III11-il024 A-1, B-l and R 21 -l.TH-N D2 5 A- 1, R- 1 ) I, 3 2 1, 2, 3 24

TABLE 3.3.2-1 (Con t inoc<l)

ISOI.ATIott ACTUATlott IllSTRlRIENTATIOff Q VALVE CROUPS HitilHUM HlfilllER A ITI. lCAltIJ'.

U OPERATED BY OPEIMBl.E CIIAtillEIJi Ol' ERAT t ollAI.

n TRIP FUNCTION AND INSTRlttENT NtfMBER S ICilAL(a) PER TRIP SYSTEll(ts).M cot 3DITi oll ACT t utt 7:

5. SiltrTIXMN C001.ING SYSTEM ISOLATi(Ni E

y a. Reactor Vessel Water - Low, Level #1

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

(B21-LTH-N017A-1,B-1,C-1,D-1) 2, 6, 7, 8 2 .3, 4, 5 27 Is . Reactor Steam Dome Pressure - liigli 7, 8 1 1, 2, 3 21 (B32-PS-N018A,B) 2'

, e-0 W

it F.

.K-

TABLE 3.3.2-2 ps ISOLATION AC1UATION INSTRllHENTATION SETIOlllTS

'3 AI.I.t AIAHl.l; h _ TRIP FUNCTION AND INS 11t0HENT NUHRER TRIP SETPOINT VAI.UE P*

1. PRIMARY COllTAINHENT ISOLATION e

N n. Reactor Vessel Water Level - Low U l. Level #1 (n21-L1N-N017A-1, B-1, C-1, D-1) > +162.5 inchen

_ 2 +162." Inch o I

- 2. Level #2 (B21-L1H-N024A-1, B-1 and 2 +112 luclien 2 +112 inctien B21-LIM-N025A-1, B-1)

h. Drywell Pressure - litgli $ 2 psig i 2 pntg i (C71-PS-!!002 A,B,C,D)

c. Halia Stenne Line

1. , Radiation - liigli (D12-RM-K603 A, B, C, D) 13x full power backgrounil 1 3.5 x full powei hnch gi euuni

2. Pressure - Low ,} 825 psig 2 825 pain 3 (il21-PS-Il015 A ,B,C ,D)

3. Flow - liigli 1 1407,of rated flow < 1407. of i nt eel (1121 -<lP1S-!!006 A,II,C ,U ; 1121 -dPIS-11007 A ,11,C ,0 ; 1121 -dPIS-t100tl .3,ll,C ,0 ; ami 1121 -dPI5 -11009 A ,11,C .0;

d. Main Stenni 1.ine Tunnel Tennperature - Illgli 5,200" F $ 200" F

, (R21-TS-N010 A, B, C, D; B21-TS-Noll A, B, C, D; B21-TS-N012 A, n, C, D; and n21-13-Nol3 A, B, C, D)

e. Condenser Vartsinn - Inw 2 7 inches lig Vacuum >/ Inchen lig (B21-PS-fl056 A,B,C,D) vncinun Ei g f. Turtaine Riilldling Area Tennp. - liigli < 200" F 1 200" F Q- (521-TS-3225 A, B, C, D; R21-TS-3226 A, B, C, D; R21-TS-3227 A. R, C, D; 3 B21-TS-3228 A, B, C, D; B21-TS-3229 A, R. C, D; R21-TS-3230 A, B, C, D; B21-TS-3231 A, B, C, D and B21-TS-3232 A, B, C, D)

,- ._ y . . , , , - - - - - ~

T_ABl.E 3.3.2-2 (Continuedl I IS01.ATION ACTUATI0li INSTRUNENTATION SETroill1S -

i) ,

AI.lDWAnl.E TRIP FUNCTIO'l AND INSTRUMENT N'1HBER TRIP SETrolHT _ val.llE

2. SECONDARY CONTAINHENT ISOLATION 9

If a. Reactor Building Extiaust Radiation - liigli < 11 inr/hr < 11 int /lir

- (D12-RM-N010 A, B)

Is . Drywell Pressure - liigli $ 2 psig < 2 pelg

( C/1 -PS-il002 A ,II,C ,D)

c. Reactor Vessel Water

evel - 1.ow, Level #2 > +112 luches > +I12 luche (B21-1.1N-H024A-1, B-1 and B21-L1H-N025A-1, B-1) I u 3. REAC1DR_ WATER CLEANUP SYSTF11 IS0lATION o

u a. A Flow - Higli i 53 gal /niin 1 53 unl/ min g

e (C31-dFS-H603-1A, IB)

Is . Area Temperature - liigli $ 150" F (C31 -TS-H600A, B, C, D, E, F) $ 15tl" F

c. Area Ventilation Temperature A Temp - liigli $ 50" F $ Su" r (C31-TS-N602A, B, C, D, E, F)

d. St.CS lultiation (C41A-SI) HA NA h' e. Reactor Vessel Water - 1.ow, I,evel #2 > +112 inclien > +111 leichen u (B21-L1H-NO24A-1, B-1 and B21-L1H-H025A-1, B-1) _

l t.t.

,, - , ~ -

.3

, TABLE 3.3.2-2 (continueil) cM

[j 11QIAf10N AGilAT1@LEt1[]URi2[

f TALL.Of[_S1[P0_lj[M

,'i p Al.IJMABl.E TRIP RINCTION AND INSTRUMEIT NUtlBER 'IRIP SETPOIliT _VA_l.UE ,_

s; 5. SiluTtxAct COOLING SYSTDI ISOLATI0tl H

" a. Reactor Vessel lister - Low, Level #1 > +162.5 Inclies > +3c2,5 in.l...n (B21-L1M-N017A-1, B-1, C-1, D-1) l 15 Reactor Steam Dome Pressure - liigli < 140 psig < l4n pa g ,.*

~

(B32-PS-N0181, B) k' s.

M u

0

.O

..-, 3..s..9. 2

57_AT:0N EvF-'IM F2E?T:EE TIE r ? r"Nc : : AND ':E ??_MN N'.MER FI5?ONSE T E / Seceni.a )

1. ' ?RDe.ARY CON"AI?,MNT IST ATION

a. Reac:or Vessel 'n'a:er Level - 1.ow

1. Level #1 (321-LT-N017A-1,5-1,C-1,D-1)

(E21 7':M-N017A-1,3-1,C-1,D-1) 113

2. i. eve; u.?

(E::1-LT-N024A-1,5-1 and 321-LT-N025A-1,B-1)

(321-L M-N024A-1,B-1 and E21-LTM-NO25A-l,B-1) 5.1. 0 **

b. Drywell Pressure - High (C71 -?S-N002 A ,5,C ,D) 113

c. Main Steam Line

1. Radiation - Eigh* 11.0**

(D12-RM-K503A,3, C, D)

2. Pressure - Low (521 -?S-N015 A ,5,C .0).

113

3. Flow - Righ (521 -dF IS-N006 A ,3,C ,D ; 521 -d?!5 -NC07 A ,5,C ,0 ; 40.5 "

521-dF 5-NC08 A,3,C ,0 anc 521 -d?!5-NC05 A,3,:,3) -

d. Main Steam Line Tunnel Temperature - High 113 (321-TS-N010A, B , C , D; B21-TS-N011A, B , C , D; 321-TS-N012A, B,C, D; and 321-TS-N013A,3,C , D)

e. Condenser Vacuum - Low (521 -PS-405i A ,3,C ,C) -

$13 4

I l 3R"NS'a'ICK - UN!! 1 3/4 3-22 Amendmen: N.

i l

TAELE 3.3.2-3 entinuedi 250* AT!O'; SYI"' 1 ES?O:*SE TIE

"!?

. C*F'ON ANO !NSU.TEh"" N*.'EEE RES?CNSE T!E iSe: ends'-

1. PR" MARY CCh""AINEh"" ISO!.ATION ( Ocetinued)

f. Turbine Building Area Tempera:ure - High NA (B21-TS-3225A,3,C,0; 321-TS-22."C A, ,1,3; B21-TS-3227A,E, C,D; E21-TS-322SA,3,C,D; 321-!S-2229A,3,C,D; E21-TS-3230A,E,;,0; 321-TS-3231A,3,C,0; 321-!S-3232A,3,C,D)

2. SE CONDARY COh"rAIhTh"" IS7dTION

a. Emactor Building Exhaus: Radia:Lon - High * <_ 13 (D12-RM-N310A,B)

b. Drywell Pressure - Eigh (C~/1 -P S-NCO2 A ,3,C ,D )

< 12

c. Rese:or Vessel *4ater Level - Low, Level #2 (E21-LT-N024A-1,B-1 and E21-LT-N025A-1,B-1)

(321-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 5,,1. 0=

BR135*'ICK - l' NIT 1 3 / /. 3-22A Amendmen: No.

i

t T.:l*_I . : .1 - :. c:s-:inued; ISCLAT:0N SYE2 M ?2??ONSI TIE

-"!. ? 7'_r* 0N AND 'N!3*.T.:.XT N""3EF. FI5?ONSE T M ' S e e er.d s i

3. FI_ COP. 'd!"""P. CLEld.~O EY?"TM ISCLATION

a. a Flow - Eigh ( C31-d?S-N603-1A,1B) 113

b. Area Tempera:are - High 113 (C31-TS-N600A,3,C,D,E,F)

. Area Ven:ilation Temocra:ure 6 T - Eigh 113 (C31-TS-N602A,5,C,0,E,T)

d. SLCS.Initia:iun (CalA-SI) NA

e. Raaetor Vessel *='a:er - Low, Level #2 (321-LT-N024A-1,5-1 and 321-LT-N025A-1,B-1)

E21-LTM-N024A-1,B-1 and B21-L3.-N025A-1,3-1) <1.0**

4 CORE STA',*D3Y COOLING SYS'" EMS ISOLATION

a. Eigh Pressure Coolan: Injec: ion Isolation

1. EPCI Steam Line Flow - High (E41-dPIS-N004 and E41-dPIS-N005) 113

2. HPCI Steam Supply Pressure - Lov 113 (E41-PSL-N001A,B,C,D)

3. HPCI Steam Line Tunnel Tempera:ure - Eigh $13 (E41-IS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488 and E41-TS-3489)

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

5. HPCI Turbine Exhaus: Diaphrag= Pressure - High NA (E41-PSH-N012A,3,C,D)

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

7. HPCI Steam Line Area 6 Temp - High NA (E51-dTS-N604C,D)

8. Emergency Area Cooler Temperature - High NA (E41-TS-602A,3) 31".NSk*ICK - UN!! 1 3/4 3-23 Amencmen: No.

1 I

M

TA2*_I 3.3.0-2 :C n:inued) 7 ISCLATION SYS*'IM ?IS?ONSI T!E

'"?.!? ?*2 C"*!CN AND INS 7"EN"' NL*S ER PISPONSI T!E e Secends 1

b. React = Core Isolation Cooling System Isolation

1. RCIC Stea= Line Tiow - Hign (E31-cPIS-14017 and E51-cF:5-tt018)

NA

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

3. RCIC' Steam Line Tunnel Temp - High NA (E51-TS-3319; E!1-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355 and E51-TS-3467) 4 Bus Power Monitar (E51-K/.2 and E51-K43) NA

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. ROIC Steam 1.ine Area a Temp - High NA (E51-d s-NiO4A,B)

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

9. RCIC Equipment Room a Temp - High NA (E51-dTS-N601A,3)

5. SHL':'DOWN COOLING SYSTEM ISOLATTON l

a. Reactor Vessel TJacer level - Low, Level #1 l ( B21-LT-N017 A-1, B-1, C-1, D-1 ) NA

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

b. Raactor Steam Dome Pressure - High NA (B32-PS-N01SA,B)

Radiation monitors are exempt f rom response time testing. Response time '

shall be measured from detector output or the input of the firs t electronic comoonent in the channel.

" Isolation actuation ins trumentation response time only.

BRUNS **ICK - 1.WI 1 3 /t. 3-2t. Am ndment No.

, - . , ,, e-

Q TABLE 4.3.2-1 ISOLATIOli ACTUATION INSTRUHENTATION SURVEII.I.AllCE REQUIREllEllTS N

Q CilANNEI. OPE H AT 1 e el Al.

y CilANNEl. FilllCTIONAI. CifAllNEl. C(ellil III8ti?; lli WilII:ll TRIP FUNCTION AND INSTRl!HENT 11UHRER CllECK TEST CALIBRATitN4 Si!RVEll.I.Alla:E Hl:4ltllit!.It

l. PRIMARY C(WTAIHtENT (SOLATION G

fl a. Reactor Vessel Water Level - Low r 1. I.evel #1 (B21-LT-N017A-1,B-1,C-1,D-1) HA(,) i:A R(g,)

(B21-LTH-N017A-1,5-1,C-1 D-1) D H H 1, 2 'l

2. Level #2 (D21-LT-N024 A-1,11-1 and NA(") NA R II'I B21 -I.T-N02 5 A-1. B-1 )

( B21 -1.TH-Il024 A-1, B-1 and D H !! l. 2, .I B'Pl-I.111-N02 5 A-1, B-1 )

R b. Drywell Pressure - Illgli

(C71-l'S-fl002 A,B,C,0) NA l'l Q I , 2, 1

$J

c. Main Steami Line

1. Rad ia t ion - lii gli

( DI 2-RH-K603 A, R , C, D) D W R I, 7, I

2. Pressure - 1.ow (H21 -PS-t101 S A ,li,C ,0) NA l1 Q l

3. 1 low - liigli .

IIA 11 Q 1 (1121 -dPIS-11006 A ,D ,C ,D; B21 -dPIS-11007 A ,Il ,C ,D ; B21 -dPIS -!!008 A ,B ,C ,0 ; and B21 -di'l S-1100') A .tl C, D) 0 p.

.s

TABI.E 4.3.2.-l (Continued)

IS0tATION ALTUATION INSTRUHEttfATION SURVEILIANCE REQUIREllENTS g CIIANNEI. Olt.it AT I till AI.

ta CifANNEL FUNCTIONAL Clif.HNEl. CONNITItt35 Ill Willt:N M TRIP FUNCTI(N AND INSTRtRIENT NUMBER CilECK TEST CALI BRATI Off

.S._tfR.VE

. ll.LANC_E H_l.81t.il~H.l._:l.'

e 1. PRIMARY CONTAINfENT ISOLATION (Continued)

O g d. Hain Steam Line Tunnel

~

Temperature - i!!gh NA H R 1, 2, 1 (B21-TS-H010A,8,C,D; B21-TS-N0llA,B C.D; B21-TS-H012A,B,C,D and B21-TS-N013 A,B C.D)

e. Condenser Vacuum - Low (il21-PS-fl056 A,B,C,0) NA M R 1, 2*

I. Turliine Butiding Area Temp - Illgh NA H R 1, 2, 1 (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; D21-TS-3228A,B,C,D;

, B21-TS-3229A, B,C,D; B21-TS-3230A, B,C,D; B21-TS-3231 A, B,C, D and 1121-TS-3232A,II,C, D)

N ti>

a i

.a,

,5 #When reactor steam pressure >500 peig.

J i

e

TABl.E 4.3.2.-1 (Continued)

IS01.ATIOtt ACTilATI0tt INSTRUMEt{TATION SilRVEII. LANCE REQUIREHEllTS us y CilANNEl. Ol'EltAT lot l Al.

f,I CilANNEl, FUNCTIONAI, CllAtlNEl. CONillTIONS fil WillCil M TRil' FilllCTIOtt AND INSTRiitENT NiltlBER CllECK TEST CAI.IllRATION SilRVEll.LAllCE REQlllHlil!

N

, 2. SECONDARY CotTTAINtEffr ISotATION c*

,N a. Reactor Building Enliaust

'! Radiation - liigli D H R 1, 2, 3, 5 and *

(DB2-RM-N010A,B) le . Drywell Pressure - liigli (071-l'S-14002 A ,11,C ,0) NA M q i , 2, 3

c. Reactor Vessel Water f.evel - Iow, f.evel #2 m (821-LT-N024A-1,H-1 and NA NA R D B21-LT-H025A-1,H-1)

(H21-1.TH-N024A-1,B-1 and D H ll I , 2, 3 u B21-1.TH-N025A-1,H-1) l.

'l . HEACTOR WATER Cl.EANilP SYSTEH ISOLATION

a. A Flow - liigli D H R 1, 2, I

( C11 -d FS-Il603-I A, I n) le . Area Tempe rat ure - lii gh flA H H 1, 2, 1 (Gil-TS-Il604A,R,C,D,E F)

N r. Aren Ventflatton A Temp -

@ lii gh (Cll-TS-fl602 A, B,C, D,E, F) NA H H 1, 2, !

eS

.'t Allin-(('liand l i ng i r raill a t ed fuel in flie secondary contalument .

l

4 e

TARI.E 4. 3. 2-1 (t.on t i nued)

ISol.ATION ACTilATION IllSTRUllEffrATION SURVEILLA _EE HEQUIREllEllTS E CIIAilllEI. Ol'E H ATIIW4 Al.

O CllANNEl. FLINCTIONAL CIIAllllEl. CollDITIONS IN Wille:ll

'_l]MP__ FIINCTIOle AND INSTRUMEllT Nilt1HER CIIECK . TEST CAI.I BH ATIOll SURVEll.l.ANCE HEylilltElj o

'I . HEACTOR WATER Cf.EANilP SYSTEH ISOLATI0li (cont inneil)

E Il sl . SLCS fnitiation (C41A-SI) NA R liA 1, 2, 3 e

e. Heactor Vessel Water Level -

1.ow , Level #2 (H21-LT-N024 A-1, B-1 and NAg ,) NA R 821 -I.T-Il02 5 A-1, B-1 )

(H21-LTH-H024A-1,B-1 and D H H 1, 2, 3 R21-LTH-N025A-1,B-1)

Me Y

3-a 5

a,

TARI.E 4. 3. 2-1 (Continucil)

ISOI.ATI0t1 ACTUATION IllSTRUtEttrATION SURVEll.I.ANCE REQUlHEIENTS Q CllANNEl, OPERATIONAI.

?! CllAllNEL FUNCTIONAL. CllANilEl. CONillTI0 tis IN WillCil N THil' FilNCTION AllD INSTRIENT NtMBER CllECK TEST CALIBRATION SURVEll.I.AllCE REQUlHED 7:

5. SilltflMMil C001.ING SYSTEH ISOLATI0H r-d

'j a. Reac t or Ves se l Wat e r - Low, r I.esel #1 (B21-LT-H017A-1,B-1,C-1,D-1) NA ,) NA R

( H 21 -I.TH-N017 A-1, B- 1, C- 1, D- 1 ) D H H- 1, 2, 3

h. Re ac t o r S t e am Doine Pressure liigli (B32-PS-N018A,B)

NA S/II*, H R 1, 2, 3 u

y

't

's a II not performed wittitu tlie previous 31 days.

(a) Tlie t ransmit ter cliannel clieck is satis fied by tlie trip unit channel check.

A separate t ransmitter check is not required.

(1. ) Teansmitters are exempted from the snonthly channel calibration.

hI a

O.

'4

.U

SD -

TABI.E 3.3.3-1 y,

DiERCENCY CORE C001.ING SYSTlH AC'IUAT10tl INSTRilHENTAT10L1 y1

I HINIHlIH lilitillER Al'PLI CAhl.E OPERARI.E CIIANNEl.S OPERATIOtIAI.

h TRI P I'llNCTION ANil INSTRllHErlT NUHilER PER TRIP SYSTEft CutilllTJ O:IS ACTION a

M l. CORE SPRAY SYST9{

e

a. Reactor Vessel Water Level - Low, Level #3 (B21-LT-NO31A, B, C, D)

(ll21-I.TS-NO31A-4, B-4, C-4, D-4) 2 1,2,3,4,5 30 ti . Reactor Steam Ikame Pressure - Low (Injection Permissive)

(ll21-PT-NO2iA, B, C, D)

(ll21 -P1N-NO2 t A-1, 11-1, C-1, D-1) 2 1,2,3,4,5 31' (ll21-PTS-NO2tA-2, B-2, C-2, D-2) t ak s' c. Drywell Pressiere - liigli (Ell-PS-N0llAB.CD) 2 1, 2, 3 30

d. Time Delay Relay 1 1,2,3,4,5 31

e. Ilus Power tioni tor f(E21-KI A,15) 1/Isus I,2,3,4,5 32

2. l.PCI HolJE 01' RilR SYS'lEH

a. Daywell Pressure - Illgli

( Ell-PS-fl011 A ,B ,C ,1))

U 2 1, 2, 3 30 a

D-li . Reactor Veunel Water f.evel - la>w, Level f3

Z (ll21 -I.T-flo ll A, II , C, D) 0 A

. (ll21-l.TS-NOliA-4, B-4. C-4, D-4) 2 1,2,3,4.5 A

30 Afin t applicatele wisen two core spray nys t.cm autssys t ems are Ol'ERARI.E por Speci fica t losi 3. 5. 3.1.

Alaim Only.

h

u TAlli.E 3. 3. 3-1 (cont inued)

EMERCENCY CORE C001.ING SYSTEM ACTUATI0ti IllSTRIlllENTATION

?$

g HINIMUM NIJIIHER A PPI.I CAHI,E e

OPERABI.E CilANNEl.S OPERATIDtlAI.

h TRIP FilNCTION AND INS'ililAIENT NUNHER - PER TRIP SYSTEH Citf DITIOllS ACTION e-- 2. l.PCI HODE OF MilR SYSTEH (continued)

c. Reactor Vessel Sliroud I.evel (Drywell Spray Permissive)

(821-I.T-NO36 and B21-I.T-NO37)

(H21-I/TH-NO36-1 and B21-LTH-NO37-1) I I, 2, 3, 4a. 5* 31

d. Reactor Steam Dome Pressure - 1.ow (Injection Per-missive)

(H21 -PT-NO21 A, B, C, D)

(Il21 -P111-H021 A-1, B-1, C-1, D-1)

(H21-PTS-H021A-2, B-2, C-2, D-2) u p 1. EllR Pump Start and LPCI Injection Valve Actisation 2 1, 2, 3, 4*, 5^

2. Recirculation Loop Piump Discliarge Valve Actuation 2 31 1, 2, 3, 4*, S'- 31

e. RilR Pennp Start - Time Delay Relay 1 1, 2, 3, 4*, 52 31

f. Ilus Power Honitorf (Ell-K106A, 11 ) 1/ ins 8 1, 2, 3, 44, $6 32 kY ANot applicable winen two core spray systein sailisystems are OPERARI.E per Speelliention 3.5.3.1.

U # Alarm only.

,0,

)

e

i

TAHLE 3.3.3-1 (continued) en PJ DIERCEllCY CORE COOLING SYSTI41 ACTilATION INS 11tUtlEllTATIUlf 4

vg

HIN! HUM NUNNER A PI'LI CAllt.E

,1 OPERARI.E CilAllNEl.S 9 TRIP l1RICTIOli AllD INSTRUMENT llUHl1ER OPERATIONAI.

PER TRIP SYSTEM CONillH ONS ACTION q 3. HPCI SYST131 Ni d

a. Reactor Vessel Water Level - Low, Level #2 (B21-LT-fl031A, B, C, D)

(H21-L111-Il031 A-1, B-1, C-1, D-1; H21-LTS-H031 A-2, 2 1, 2, 3 H-2, C-2, D-2) 30 Is . Drywell Pressure - liigli (El l-PS-fl011 A,B ,C,D) 2 1,2,3 30 u

p c. Conilensate Storage Tank Level-l.nw (E41 -1.S-Il002, 2** 1, 2, 3 E41 -I.S-IlOO 3) 33 b

N el . Suppression Chamlier Water Level-High (E41 -I.Sil-NOISA, R) 2**

e. 1, 2, 3 33 Bus Power Honi tor # (E41-K55 and E41-K56) 1/lius I, 2, 3 32

4. yg

a. firywell Pressure - liigli, coincialent with

( El l-PS-t(010A,B ,C,D) 2 1, 2, 3 30 i

Y a

J h. Reactor Vesuei Water f.evel - I.ow, f.evel #3 h (H21 -l.T-Il031 A, 11 , C, D) 2

s, (It21 -l.TS-NO31 A-3, 11-3, C-3, D-3) 1, 2, 3 30 U -

Alarm only.

- Piovlites sip,nal Io 111'C1 punip auct ton valves only.

TABLE 3.3.3-1 (continued)

% DfEltCENCY CORE COOLING SYSTEM AC'IUATION INSTRUHENTATION Q

III HINIIIUM NUHilER APPI.I CAhl.E

'r, 8

OPERARLE CilAtiHELS - O PERATIO'IAI.

TRI P RHICTION AND INSTRUMENT NUHREK PER TRIP SYSTDI CONDITIONS ACTION N 4. AIG (continued)

N

.. c. Reactor Vessel Water Level - Low la vel #1 1 1, 2, 3 30 (ll21-LT-N042A, B; B21-LTH-ND42A-1, 0-1)

d. ADS Timer (821-TDPU-KSA, B) 1 I, 2, 1 31

c. Core Spray Puinp Discliarge Pressure - liigli (Pennissive) 2 1, 2, 3 31 (E21-PS-H008A, B and E21-PS-N009A, B)

f. RHit (LPCI MODE) Pump Discharge Pressure - liigh (Pennissive)

(E11-PS-N016A,B,C,0andE11-PS-N020A,B,C,D) 2/ pump I , 2, 3 3j j h u. nus Power Monitor # (H21-KIA, B) 1/ lain I , 2, 3 32 l

Y y

MINIMUM APPL.lCSDLE TOTAL N0. CllANNELS CllANNELS OPERATIONAL OF CllANNELS TO TRIP OPEMBLE CONDITIONS ACTION

5. LOSS OF POWER '

a. 4.16 kv Emergency Bus :n p' Undervoltage (Loss of Voltage) 1/ bus

,, I; . 4.16 kv Emergency Bus 1/ bus .1/ bus 1, 2, 3, 4 ## ,5 ## 34

y. Undervoltage (Oegraded Voltage) 3/ bus e.

2/ bus 2/ bus 1, 2, 3, 4 ## ,5 ## 35 x # Alarm only.

E 1

ffRequired when ESF eqtilpnent is required to be OPERADLE.

- .g

[

?; .. ,)

~ , ,

TABl.E 3.3.3-2 '

u,

~

9f p) plERGENCY CORE C001.ING SYSTElf ACTUATION INSTRUtlENTATioll SliTI'OlllTS

, A1.IAMAHI.E

( I TRI P FilHCTION AND INSTRUMENT NUHRER TRIP SETPOINT VALUE I. CORE SPRAY SYSTDI fl C,, i n. Reactor Vessel Water Level - Low, Level #3 > +2.5 luchen > +2.5 lin: lien

- (ll21-1.TS-NO3IA-4, B-4, C-4, D-4) alsuve top alsove top l fuel gulile fuel-gulile l Is . Reactor Steam Dome l'ressure - Lo.:

(R21-PTS-H021A-2, B-2, C-2, D-2) 410 _l 15 pelg 410 1 15 psig

c. Drywell Pressure - litgli .,$ 2 pelg < 2 psig (Ell-PS-N0llA,B.C,0)

Y u, d. Time Delay Relay 14 < t < 16 aces 14 < t < 16 secs s's s' e. Bus Power Hout f or (E21-KI A, B) IIA IIA

2. Litt MODE OF HilR SYSTEll

a. Drywell Pressure - liigli < 2 pelg < 2 pelg (Ell-PS-NollAR.C.D)

b. Reactor Vessel Water Level - I.ow, I.evel #3 > +2.5 luchen > +2.5 luchen (Il21-Ilrs-H03l A-4, B-4, C-4, D-4) " "* I"E " I '"" " "I' f,

, fuel gulile fuel guhle N

jj c. Reactor Vessel Shrouil I.evel >,

53" below t up > 5 't" below top te (1121 -1J111-11036-1 aml R21 -IllH-N017-1) fuel gulite fuel gulite l v.

_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - m - _ _ _ _ - - _ . m -

TARI.E 3.3. 3-2 (continued) g M1ERCENCY CORE C001.ING SYSTEM AC'lVATION INSTRUMENTATICII SETP0lNTS U

p Al.IJ RIAnl.E ti IT!IP FUtlCTION AND INSTRUllENT NUHBER TRIP SETP0lHT JAl.IIE 9

e d. Reactor Stemen Ikime Pressure - Iow 0

ll 1. RilR Pwnp Start and I. CPL Injection Valve Actuation y (B21-PTS-11021A-2, B-2, C-2, U-2) 410 i 15 psig 410 1 15 pelg l

2. Recirculation Pump Discliarge Valve Actuation (B21-I"DI-N021A-1, B-1, C-1, D-L) 310 1 15 pelg 310 1 15 pelR l

e. RIIH Pump Start - Time Delay Relay 9<t< 11 seconds 9<t< 11 secouils

f. Rus Power Monit or (Ell-K106A, B) NA NA u

l' Y

Y' N

a R

a,,

)

Q .-

TAlli.E 3.1. 3-2 (cont inneil)

,YIJ

[} E!!ERCEllCY CORE C00LINC SYSTEM ACrilATION INSTRitlENTATitW SETrollirS r

f';; Al.l.OWAllt.E Tit lP FilHCriori ANI) INSTittfMEllT HillinER THIP SETPHINT VAI.llE et

'I . IIPCI SYSTEH

a. Reactor Vessel Water IAvel - Low, I.evel #2 > +112 inclies aliove > +112 inctien nliove (821-I.TS-NO31A-2, 11-2, C-2, D-2) - top fuel genitle - t up fuel gulate 1, . Drywell Pressiere - liigli -< 2 pelg < 2 pulg (cli-Ps-nenA,B,c,0) -

t' c. Conitene.ite Storage Tank I.evel - I.nw > 23'4" (E41-I.S-N002. E41-I.S-N003)

- ~> 2l'4" Y

l;l it . Suppresalon Cliaml>cr Water I.evel - Illgli* < -2 feet < -2 feet (E41-I.Sil-Hol5A, II) ~

~

c. Ilus Power Honitor (E41-K55 ani! E41-K56) N/A N/A

4. ADS

a. Drywell Pressure - Higli ~< 2 psig <~ 2 pulg (Ell-PS-N010A,8,C,D)

L 9eactor Vessel Water I.evel - I.ow, I.evel #3 > +2. 5 Inctieu > +2. 5 lucima (ll21-Ill'S-NO31 A-3, 11-3, C-3, D-3) ~ ~

c. Iteactor Vessel Water I.evel - 1.ow, i.evel #1 > 1162.5 inclien > 4162.5 luclien (ll21-Ilfil-N04 2A- 1, 11-1) ~ ~

Ei 8 it . ADS Timer (il21-Ti>Pti-KSA, II) < 120 seconiin O

$ 120 serontin

e. Core Spray Pump Dlucliarge Pressure - liigli )

, 100 psig ,)1830 pnin

. 'A (E2I-PS-N00tlA, il an(I E21-PS-N009A,11)

I "

f. ItHit (LPCI Hmle) rump niacliarge Pressure- Niali ~> 100 pnig ~

100 pulg l (Ell-PS-Nul6A, B, C, D ans! Ell-PS-Il020A, II, C, 11)

Suppiesslost cleamtier water level zero in tlie torun cent erillie minian I incle.

e i

TAHLE 3.3.3-2 (coniinueil) w FNERGENCY COPE C001.ING SYSTEM AC1UATIOtt INSTRUMENTATIOli SETPOINTS i'j q AI.I.0WA RI.E

,sg TRI P FUNCTION AND INSTRUMENT NUMMER TRIP SETFOINT VAI.UE il

4. ,A,In (continued)

8. Bus Power Honttor (B21-KIA, B) NA NA

~

5. LOSS OF POWER -

a. 4.16 kv Unergency Bus Undervoltage a. 4.16 kv Basis - 2940 + 161 volts (Loss of Voltage)* 2940 + 315 volts

b. 120 v Basis - 8414.6 volts 84 1 9 volts

c. < 10 sec. time delay < 10 sec. time delay

b. 4.16 kv Emergency Bus Undervoltage a. 4.16 kv Basis - 3727 + 9 volts 3727 + 21 volts (Degraded Voltage)

~

b.*120 v Dasts - 106.5 + 0.25 volts u

D 106.5 t 0.60 volts i c. 10 1 0.5 sec. time delay 10 i C0 sec. time delay u

b.

T ihis is an inversTtime delay voltage relay. The voltages shown are the maximum that will not result Ir. a trip. Lower voltage conditions will result in decreased trip times.

II n

It a..

O TARI.E 4. 3. 3-1 Ef t:RCE14CY CORE COOI.ING SYSTEM ACII!ATIOll INSTRiftt;t(TATION SlfRVEILI.ANCE REl}tilREENTS tn CilANNEl. Ol'E RAT i tmal.

ed CIIA!INEl. FIR 4CTit W AI. CilAl4NFl. CitiblTite(S IN WillCil Il TR il' l'IfNFi lON AND INSTRIRf. fir NIIHRER CllECK TEST CAI.I DRATIOtt SifRVI:ll.l.AllCE RrtMHfEll e 1. C(*E SPRAY SYSTEH

.U

j

a. Reactor Vessel Water Level - Low, i.evel #3

( R21-LT-NO31 A, B,C D) g NA NA R

( H 21 -ilrS-NO3 t A-4,5-4, C-4. D-4) D H H I,2,3,4,5 li . Reactor Steam Dnsee Pressure -

( B21 -1"r-N021 A , B , C ,I)) NA

IIA RI y '

( B21 -l'rH-N021 A-1, B-1,C- 1, D-1) D H H 1, 2, 3, 4, 5

( R21 -l'IS-14021 A-2, B-2, . -2, D-2 ) D H H I* c. Ilryue!I Pressure - ll1gli U (Eli-PS-HollA,B,C,D) HA N 9 1, 2, 3

<l . Time ine lay Relay NA R R 1,2,3,4,5

c. Hus Power Honitor (E21-KIA H) HA R NA 1, 2, 3, 4, 5

2. IfCI HOIE Ol' RilR SYSTEli k a. lit ywell Pressure - lii gli

( ( El l -PS-no l l A ,8,c ,0) NA M Q ] , 2, 3 2

il X-

((i)

'l l n- t s ansmi t ter cleannel clic ek is satisfleil lay the trip unit cleannel clieck. .

A separate t ransmi t ter clicek is not resgu i r eel.

(I.) T ansmitters ni c exen.pt eil f rimi time montlity cleannel calltinat ion.

c.

TABI.E 4.3.3.-l (Con t isinett)

E)ERGENCY COME COOI.ING SYSTEH A("TilAT10H INSTRUIElfrATION SIIRVEll.I.AllCE HEQUtitEENTS S! CilANNEI. IKE RATit tlAI.

Il CilANNEL FUNCTIOHAI. CIIANilEI. CONDITI4WIS IN WilI8'll U

?*.

1Hir IISICTION AND INST?.UFENT NUMBER CilECK ,

TEST CAllitHATI0ll SilRVEll.l.ANCE HlblilHEli

2. I.PCI HODE OF MilR SYSTEH (Continued)

I2

'j li . Reactor Vessel Water Level - Low,

- I.evel #3 (ll21-LT-H03 t A,8,C.D) NA(a) NA R II* )

( B 21 -1.TS-H031 A-4. B-4,C-4,1F4) D H H 1, 2, 3, 44, 5*

c. Henctor vessel Slaroud Level (B21-LT-NO36; B21-1.r-NO31) NAI *I HA R (li) u (B21-I.TM-NO36-1 and I) H H 1, 2, 3, 44, 54 D I!2 I-LTH-NO3 7- 1)

d. Reac tor St emme Donne Pressure - Low U (ll21 - PT-N0? ! A , B ,C ,I)) NA(a) NA R II' }

l

1. Rllit Pump Start and LPCI Injection Valve Actuation

( H21 -l'fS-H02 t A-2, B-2, C-2, D-2 ) D M H 1,2,3,4*,56 l

2. Recirculation I.oop Pinnp Discliarge Valve Actuation

( H 21 - PTil-NO2

A-1, Il- 1, C-1, D-1 ) D M H 1, 2, 3, 4 a , sa l

e. RilR Pump Start-Time Delay Relay flA R R t , 2, 3, 4 * , $*

f. Itua Power Honitor (Ell-K106A,B) NA R HA 1, 2, 3, 4 * , %

S I', 2 tiot applicalile wisen

wo core spray sys tein sulisystems are OPERARI.E per Speci ficati nen 3.5. 3.1.

v.

." ( a) 'llie t ransmi t t er cliannel clicck is sat is fied ley clie t. lp unit cleannel clieck.

A sepainte a ransmi Ier clierk is not regulsed.

(ii) Tennsmi tters ase exempt ed in om clie montlily cliannel callieration.

e TABLE 4.3.J -l (continueiQ FLENCEllCY CORE CNI.ING SYSTEM ACTIIATitti I NSTRUtENT AT I ON StIRVE ll.I.ANCE It Es}til REIE NI]

6 f CilANNEI. ' iH'E RAT I(IllAI.

g CIIA NfE L FUNCTIONAI, CilANtEI. CateDITIONS IN Wilit38 g TRIP FitlCr8044 AND INSTRiffENT NUMMER CllECA 17.ST CAI.1HRATIOli SURVEII.I.ANCE REQtilHED

1. lil'CI SYS1EH n a.

es Reactor Vessel Water level - 1.ow ed I.evel #2

( R 21-l.T-HO 31 A , B,C, D) NA g g NA R (B21-LTH-NO31A-1,B-1 C-1,D-1) D H H 1, 2, 3

( H21 -I.TS -H031 A-2, 8-2, C-2, D-2 ) D H H ti . Drywell Pressure - liigli (E11-PS-N011A,B.C,0) NA M 0 Ie 2. 3

% s-u c. Condensate Storage Tank I.evel g low (E41-1.S-N002, E41-I.S-H003) HA H E) 1, 2, 3 it . Suppression Chandier Water I.evel - ,

litt h

( E41 -lJil8-Il015A , R) NA H f) I , 2, I

c. Itus l' ewer Honitor (E41-K55 and NA R NA 1, 2, 1 i:41-K%)

4. Ayi

, n. liryuel 1 Pr essure - Hi p,h h (Ell-PS-N010A,8.C D) NA M Q 1, 2, 3 N

i .i l the t ransmi t t er channel check is satisiteil by the tilp unit cliannel clicek.

A sepasate t r ansmi t t er check is not requireil.

(I.) Transmit ten s nic cucinpt eil f roni the amntlity channel calibrat lon.

o TARIE 4. 3. 3-1 (Continued)

, DERCENCY CORE COOLlHC SYSTEH ACTllATION INSTRIIPERTATION SURVEll.lAtlCE REQiflitEHENTS ps I$ CilAHlf.L off.M ATI tWAI.

' U. CilANNEl. FUNCTIONAI. CilAfillEl. CONDITitWIS IN Willi:ll T4,lP_,FlitkTI(N AND INSTNUtENT HilHMEle CllECK TEST CALIBRATION SURVEll.l.ANCE REQUlHl:lf

,, 4. AliS (Cont inued) d.

r

+8 h. Neactor Vessel Water I,evel - 1.ow,

" I.evel #1

( B 21 -l.T-NO 3 t A , B ,C , D) HAI ") NA R(b)

(Il21-l.TS-N0 31 A-3,8-3, C-3, D-3) D H H 1, 2, 3

c. Reactor Vessel Water level - Low 1.evel #1 gg

( B 21 -I.T-N I4 2 A,5) NA NA R 1, 2, 3 s., ( ll21 -1.Tti-fl042 A- 1,5- 1 ) '

D H H E

al . Alls Timer (ll21-TDril-K5A,B) NA R R I, 2, 3 Y

M c. Cure Spray Pump Discliarge

> l's ensist u - lllgle NA H Q l , 2, 3 (E21-l'S-HIH)H A,B and E21 -l'S-N UO9A ,5)

f. HilR (1.t'Cl FM)DE) Pump Illscliarge l l'a cusure - liigli NA H () I, 2, 3 (El 1-PS-N0lf>A,B,C,1) and El1-PS-NO20A,B,C,D)

II g. Ilus l'ower Honi tor (B21-KI A,B) i(A R HA I, 2, 3 l

n a.

g (a) Ilie t ransailt ter clianisel check is satisfied by time t rip unit cleannel clieck.

A sepasate t ransniit ter check is not r esgu i red.

(ii) Tr ansnil l t e n s a t e e xcaipt eil fl ows the sinositlity cleannel calibration.

y TABLE 4.3.3-1 (Continued)

g EMERGEfiCY CORE CGOLiflG SYSTEll ACltlATI0fl INSTRUttENTAT10fl 511RVilLLNICE ItEQtilRE"IllIS il e

I; OPERATIONAL k! CllANtiEL C0ftD11.0NS Ill W!!ICil r: CllAN'iEL FUNCTIOfiAL CitANNEL SURVEILLAtlCE

flitiCTI0ftAL UrllT . CilECK TEST CALIRRATI0ft REQt!! RED

5. LOSS OF POWER

a. 4.16 Lv Emergency Bus NA NA R 1, 2, 3, 4*, 5*

lintlervoltage (Loss of Voltage) ,

b. 4.16 kv Emergency Bus , S tl R 1, 2, 3, 4*, Sa lindervoltage (Degraded Voltage) 2 Y

d a

'Itequireil when ESF equipment is required to be OPERARLE.

O

l TAE'.I 1.3.5.3-1 POST-ACCI"'EN" MO*!'"0RU?C INS *?.LMN"A"*0N moi 2fH NO.

OF OPERA 31.E INS'"RUMENT INS RLVENT AND INS RL*Eh"" ND'3ER CHANNELS

1. Reactor Vessel Water Level 2 (321-LI*S-NO26A,3; 321-LR-615; 321-LI-R604A,3; 321-LT-NO37 and 321-LTM-NO37-1)

2. Reactor vessel Pressure 2 (321-PI-R006A,5; C32-LPR-R608 and C32-P'*-N005A,3)

3. Containment Pressure :

(CAC-PI-2599; CAC-PT-2559; CAC-PR-1257-1 and CAC-PI-1257-1)

4. Containment Pressure 2 (CAC-TR-1258-1 thru 13,22,23,24 and C91-P602)

5. Suppression Chamber Atmosphere Temperature 2 (CAC-TR-1258-17 thru 20 and C91-P602)

6. Suppression Chamber Water lavel 2 (CAC LI-2601-3; CAC-LA-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1)

7. Suppression Chamber Water Temperature 2 (CAC TR-1253-14, 21 and C91-P602)

8. Containment Radiation 2 (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262 and CAC-AQH-1262-1,2,3)

9. Containment Oxygen 2 (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263)

10. Containment Hydrogen 2 (CA':-AT-195b1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263)

11. safety relief valve position indication: 1/V31Ve Primary - Sonic (B21-FY-4151 through 4167 Secondary - Temp. (B21-TR-R614 points 1-11) i 3 RUNS *=' ICY. - UNIT 1 3/4 3/51 A:nendment No.

i

TARIS. 4. 3. 5. 3-1

,,, POST-ACCllENT HOtilTORINC INSTRIIHENTATION SURVEll.LAllCE REQUlHI HENTS

u IM CilANilEL CilANNEl.

U INSTHiltEllT AND INS 1RtMENT NtlHBER CAI.l HRAT IOtt CllECK-

1. Reactor vessel Water Level H R (821-LITS-11026 A,8; B21-LR-R615; B21-LI-R604A, B; j, , H21-I.T-H037 and B21-L111-N037-1) l

- 2. Heactor Vessel Pressure H R (H21-PI-R004A,5; C32-lER-R608 and C32-PT-N005A,5)

1. Containnent Pressure H R (CAC-PI-2599; CAC-l'T-2599; CAC-PR-1257-1 and CAC-PT-1257-1)

4. Containment Temperature H R (CAC-TR-1258-1 thru 13,22,23,24 and C91-P602)

5. Suppression Chamlier Atmosphere Temperatiere H R

, (CAC-TR-1258-17 thru 20 and C91-P602) 6 Suppression Chanitier Water Level H R (CAC-LI-2601-3; CAC-LR-2602; CAC-LT-2601; CAC-l.T 2602 and CAC-LY-2601-1)

7. Suppression Cham. lier Water Temperature H R (CAC-TR-1258-14, 21 and C91-P602)

II . Containment Radiation H H (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-A51-1261; CAC-AQll-1261-1,2,3 ;

CAC-AR-1262 anil CAC-AQll-1262-1,2,3) h 9 Containment Oxyr,en Concentration H R y, (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263)

N 3 10 Coin t a l nmen t flystrogen Concent rat ton 11 R ICAC-AT-1259-l; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263)

11. Safety relief valve punition indicatlon (P r i nia r y-Son i c) M R (821- FY-415/ thr's 4161)

12. :;al et y s e t ief valve po:ill ion i n.I I ca t i on (Sec on.la ry- Tempe rn t u re) M R (B21-Tft-R614 points ] thru ll)

~

TABLE 3. 3. 6.1-1

, ATWS RECIRCUI.ATION Ptfr;P TRIP SYSTEH INSTRl4ENTATIOi!

M ha:

HINIHUH NUMBER OPERABLE TRIP TRIP FIR 4CTION AtlD INSTRtRENT NUMBER SYSTEMS PER ope: RATING PUHP-El

1. Reactor Vessel Water level -

,. 1 I.ow Low, Level 2 h ( B21-LT-fl024 A-2. B-2 and B21-LT-N025A-2,5-2)

+8 B21-L111-t3024 A-2, B-2 and 821-LTH-N025A-2,5-2)

2. Reactor Vessel Pressure - liigh g (H21-PS-H045A,B C D)

V E

a a.

a so 5

e' TARI.E 3.1. 6.1-2 w

ATWS RECIRCtll.ATION PUNP TRIP SYSTEH INSTMitElfrATIOf2 SETPOINIS '

.E>

E, 11t1P alt.tWABl.E

[$ THIP FUth: TION AND INSTHl#ENT NUH8ER SETPOINT VALLE e 1. Reactor Vessel, Water Level -

ry Low low, Level 2 > +112 inclies anove > +112 inclies al.ove h

' ( B?l-LTH-NO24 A- 2,5-2 and - top fasel gulate ~ top fuel gamlele B21 -I.1N-N02 5 A- 2, B- 2) e

2. Hescror Vessel Pressure - liigli 1 1120 palg < Ic20 peelg (B21-1$-N045A,B,C,D)

M S~

?:

I it d

i' z

a' TABI.E 4.3.6.1-1 ps

.155 HECINClit.ATION Pt4IP TRIP SYSTEli INSTRUllENTATION SURVEll.l.ANCE REQUIREHEl(TS Q CilANNEl. CilAl#iEl. FlfHCritHAl. CilAt4NEl.

${ THIP FIR 4CTION ANil INSTRUMEffr NUlfftER CllECK TEST CAbillM TIG{

f

)*

l. Reactor Vessel Water level -

l.nw I.ow , f.evel 2 M ( B21-1.T-Hi:14 A-2. B- 2; B21-I.T-N02 5 A-2, B- 2) NAI " NA R(b)

!) 521 -1.TH-N024 A- 2,5- 2; B 21-IIIN-NO25 A- 2. 5-2) D H H e

2. Heactor Vessel Pressure 11181 NA H R

( H 21 - PS - N04 5 A, B, C, D)

Us~

I' 0;

W Es in) 't he e ransmi t ter channel check is ant is fled by the t rip imit channel check.

," A sepaiate t ransmi t ter check is not required.

U (b) Tiansmitters nie exempted from the monthly cliannel caltheation.

o

.c .

e..

.. : . ;. . .n. .

pc .n . sv.

- e. > :..v.e.

SURVEILLANCE REOUIREv.EN'S (C ntinuedl d .- At least ence per 13 =cntns, during shutd wn, by verifying that either:

1. The battery ca:act:y is adequate :: su::iy and =asa:ain in OPERABLE s:a us all cf the a::ual emergen:y leads f r 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months wnen :ne battery is subjectec :: a battery service test, cr

2. The battery ca:acity is ade:uate :: su::1y a du==y load of the following profile while =aintaining the battery teminal voltage >_ 105 volts.

a) During the initial 60 seconds of the test; li Battery 1 A-1 > 1056.a2 a=:eres , l 21 Battery 1A-2 > 1211.90 a=:eres, e 3h Battery 1B-1 s 1089.06 a=:eres, and

( 4 Battery 152E1042.57a=:eres. l b) During the remainder of the firs: 30 =inutes of the test; l) Battery 1 A-1 > 243.19 a=:eres , i

2) Battery 1A-2[159.10 amperes, 3h Batte y IB-1 > 176.79 a=:eres, and 4h BatteryIB-2E216.57a=;eres. l c) During the remainder of. the 3 hcur est; . - -

1 Battery lA-1 > 89.52 a. ceres, l 2 Battery 1 A-2 > 50.34 a::eres, '

3 Battery 1B-1 E 53.39 a=:eres, and

4) Battery IB-2 > 75.09 a=:eres. l

3. At the c:= lett:n of eitner of the above ests, the battery charger shall be demenstrated ca:able cf recharging its battery at a ra e of at less: 200 at:eres while su:: lying nomal 0.C. leads. The battery shall be enargee :: a:

least 95: capaci:y in 1 2* hcurs.

e. At least once :er 60 =:n:hs durt.ig snu ::w. by ve-ifyi ; :nat j the battery ca:acity is at least S05 Of :ne manuf a::urer's l rating when su:jec ed := a perf mance Ois:harge test. This

! :erfemance dis:narge :es shall be :erf:- e: su secuer.: :

I the satisfa:: cry :: :letien Of the re uirec ca::ery service test an: after nemal ecuali:er :harge.

BRUNSW:CX - UNIT 1 3/48" A.enceen: .+

l F00RORSNAL

3

si s O

[Q E l 2 C C w Ln

=. CO O -- - N == M M

>= MM m M f7 f"1 f7 H y Q aan %

elC C mas eum M M suas aan

.,J J % %

LJ c:l m LaJ c: MI er e J2= JZE *

= cl O C * * -

< .0.

>=

- . o c7 m m (9 m M M cc == == M M f7

. . . . . . . .U >=:

c -H . .

.v

.J h C

&W=

.H NN N NN N N Ju=

l LJ Z N N Ln

l e., o . . . . . .

c. c C =

M a:; o y -- - -- - - aC:o u, - -

Q zf -

C' 4

== M M M H J U all:.

>=

=tJK.

.a w 6.l Z >=

C w

Z Lt=

= c g t/') s: M

LJ 4/t m a.=

6, e

Z c: l>.- 5 a

3 kJ

==

3 3 U

==M .c 3 .c 0 5;

=,

av

c. NN - - N s

N s

v<

=

s s

N M a

>= Z bJ == EW v , o J cl: => c- L

U m

.C .Z Cl1 >= .E C a

= c C eJ

=

~

6 2LJw

. ^

o

.E

-= L.J E c. c. *, E -J c - o a > =

- >= gg3 *=

elll*

=a a:". a e m C = .:C ^ m W C >- Q O == c.

U U - > C Q w aC : O === C

a o M c

- e e/t c. J c. i/t a L .

I D".. M e w w == 3 3 e uJ t=1 H,, L = 2l* C .3 .3 .J

V. a C O Z >= N N m cc f"1 >= e. O cn=== $ - N = *

V. e c. ~C C 5 (7 w *=* =

U r-- 4.4 e w C ==*f7 U* M h c.

tJ C man .= 6 A- O

-J *= .O == 01 c3 sti C

= : .,a - na e G = .3 o o

<l: .

C -c eZ L a:C 3 ,c

>= C 3> ad ^3O m t/n U C L l C3 MN *M Q Q 4.a J > *aO CJ E> u t.4 C 0 C eC" CZ Z L-J C C . .4 L CT b e = m 6/t .G .a g- ac C

U

""3 "X 3

3 O c. M mC A

.J Z 3 3 m> g w C cC <C J:2 .Q h 6 0J 9 mCC 8 *" >= = % '% s/n C =

>= C - O s Cir= Cc"* CU - s7 Q =

C w I bML-

C" 2" c Q l c Cll C LJ 4:C >-".-

1 h c "u g 6 6J v- *== s .= - Q L y y C = Q Y CC U

U "O M A3 C llC *>Q *= g * ."ln N M C 8 mm L D .C 7 atC 6 LJ *'a (U - , .ett

,=

E .' C) J C* ** - LO 4 C N "O C Q.

6 ==

m M .C :"P O C3 m ts. m CJ L E a

> ZLUug

U C C. * ' = *

3 O 3 *C C 3 C C PW

a. =#O E O C

g CD CC C W Q. c LJ O * ' se u , 3

8Ein vt L c=

C c * = c C3 C cl1 A CD b

*O h 61 h c's Oee 1=

3 C 3 aC y P"= U C U c 30 c 6 - m 4 L eC ^ c:" *J C CC a c. 3 P-- Of - m E c3 LaJ bo = c J, c; w ;; ; c M

= mOC QC 4N 3OC- C m m =: ;ra ;;- CC A C O C O C1 L c C1 L cJ C Q

- on . .c i-.-- =.; E Z = c Ci cJ cn J cJ.= .a .c u.

L Q t#'t L ga ha a 3c gc 3 == m

= 1 :s. == > m'a; Wb L cC M == M L % 64 eJ LJ *J y

= J O c. C 6

-.=== - = = = cc 4 sC - b 6 h 1 E1 8 C- 3 3 >= > 0 0 >CC - = =

- C - C == = us .J - C == C .g > =)a > :ln .:': 5, c,,

ll"" U - a N w N >= N*"-G Z c. L c -c c:l - . .;::

O 2 U dC UC @LJ LJ O O CJ 4J tO C *d ,U t/t h3

= >g se

7 V V'1 6 *=* CE' ===* m L. c - =c - === -

>= b@ J M

CC Z = J C +CC = C C - m C ==:

O C CE *C U E C *c T =l3 Oz. T C lla= 1OC CJ Z Z M L "':

3 M

C M cw = .6 .

6. *

c . * * * == 0 * *

> C3

.C c e .= s o - =c i--

U

_J = .m aeue c c-

- = a

= c. .C c: :

~ llbC e D = j* c ata mai

>=l 4::= 6. 4.7 ) e suma UJ.': -'*Mr - U"IT 2 2/* 3 .?2 klend::ent No.

9 .

,O

W V

t e D

w = = =

a a 8o' u-2 c LJ cp d .o. t CJ o -

Ch g

sn W 5^

=.

.J g e.'. T *== M

. M C. C.

c .C c. n. e ea oo

p. ~ -

m N . e o

.,4,

_. u u i w n ~ No o

- g e +

Al vi 41 vi z vi c:

m al ,y vlAl ^! =

=

o

,A.- .

w .c m u e

r -

o I.- -

e =

e

= 6 e u .a o v,

. o .= i c c =

t l:

w ~

u e en a

e on c

u

'^ ue o

w ui e e.n

's c

5 - a w - ~

m N w s we A w a. c, a:. c. ~ o. -

a.

e oo o o

.o m ~ m u * -

~o o c m =

- u n a " -

a ::

.c.- fu. + -- - -

c Al vi al vi $.

. vi at rd vlAl al -s L o

- 2' -

.a o .

=

e a.=

w o ,--

<l" N

-= o'.

CTm'=

=

U u

w ;'s M e aan amm .l : 3 u. 3

.N O - 6

os c'l L e ug e .::: 'e' -

G

f") > Cri h e = 6 aC .o.a m

. C GJ = d D. ~* *""* 3 o w a 2 = GJ 8 CC w N to o i J ~ .a o m to - $.. .:::

a t e4*

e et aJ =

>- R i 6 Os L i w e o w 1: **

D o c. un J 8 - C j vi o ca.

v.

J SD *C -

c: c.s , J ~

m Z $3 i

<c

- > c ei en- .=i p =:. 4 W a==. e e I * .3 o c:: >ciJ 6 J us - i cm'cWu m 6 - sn. o

. .eaoL Wo ft m 8

w co 5"

w v .x Z .We in M

as b

3 .c so cJ - u =e -

CnN en C M aC eq e as .- >

lt: === c m e c: u uJ - o w

c: w J o..c *C2 e J 2 eur m J C.3 L me Me .c -l3 o=i o '>

o :c L U cm = > - i e ==u -L

<==. w .c o L U cn

^ o w w

- +J cc = = as it-

= = +d CO= -5 Cc-

- U se "D .u c c. =. Na e E- u .cn.

e a i CD cnw .oas c2 L e te e =w L

>- .5 2 <c:: C . .E *Co c== :3 sc L u

-= a: -ceu e aC .o, in eu .e~ 3. -eC :s,;' >=i. e.<: . ..C *o o w

m

- m a> o .=n ~oovo= ~ .c - - aew - e.

c.3 E en 2" e o m o 2ll

.m n- o ao.

- m .a ~ m o o =~- c .x c:

w

- e i um =,e.E z en oz oa.u >Z me :>. m ," 2,>,ED

= = f=.o zo ' L.3 m

w

= :-cm-mo a, m u i J c. 4 ,J M J mL c.

ue .

- s .,.: Lem-ma o o,a,

.2 f r w

L i- i = -a i =

W

-iL

c. .J G.) bc W C.

e c. c. o e

= -

e

.c v

.~ - c - o-c.c-c : u w

,-c-0--m-a e - - ~ ~ n. ,-

iu i

~ ~ - c.

> z o

, .=

y

.o zwu m

e .e E.w o

u

= .w e= w o

m e 3

e co .c ua -e m uow

- ee w

=

o o e o o m em o c: = = o = = -

.c u c: c2 .a E G m "

w a. . . . . o -

c. , z . .o u e as .c a

.c u -

~

a: .

2

.=- .m BP.UNS*,: K-UNIT 2 -

3/4 3-25 Amendment No. --

I

. . ~

ML20004F563

Text

= >g se

= .w e= w o

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