ML20004F563

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)

Text

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O CB C

TABLE 2.2.13 o

REACTOR PR(T ECI'lOtl SYSTDI INSTRllHEITTATinti SETroitTIS

@g gI)

C p AI.lAMAltlE d

Filt3CTlotMI. UNIT AllD INSTRllflENT NUllHER TRIP SETPollff VAIJfES I

1, Intermediate Range Monitor, Neutron Flux - liigt

$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 I3)( ')

Is. Flow Blased Heutron Flinx - liigl:

3(0.66 W F 547.)

1(0.66 W I 547.)

I#')

c.

Fixed Neutron Flux - liigt:

31207. of RATED 11tEHthl. PIMER

$1207, of PA1ED TilElunt. P(UEH T

t~

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

>t162. ' Incli. n above

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

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) 10.

Turbine Control Valve Iast ControlOilPressure-Low (g}osure.

m

> 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

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

M 1.

Intermediate Range Monitors:

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

+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 c.

Fixed Neut ron Flux-Illgli, 1207.

I 2

4 d.

Inope ra t ive I, 2, 5 2

5 9

L e.

Downscale 1

2 4

f.

LPRH 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

[q APPI,1CARI.E HINIHlit! 13tilfilER 1

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 -

II}

liigli (Cll-1. Sit-N013A,B,C, D) 1, 2, 5 2

5 9.

Turbine Stop Valve - Closure 1(8 u

4 8

)

( EllC-SVOS-I X,2X,3 X,4 X) y 10 Turlitne Control Valve Fast Closure Cont rol Oil Pressure - 1.ow 1(g) 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.

10.09 d.

Inoperative NA e.

Downscale NA f.

LPRH HA Zs' 3.

Reactor Vessel Steams Dome Pressure - liigh (B21-PT-N023A,B,C,D)

<0.55 v

(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 dnoce S

(

m E

o l

r i

8 f

T 0

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E 0

A A

c S

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E m

R_

e i

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m i

S t

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)

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S s n i

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u 0

)

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P 9

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5 n

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7

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R 1

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C t

8

)

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(

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1 t e T

7 S

s n S

1 eo 2

Y A

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7 1

m 1

5 7

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7 C

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(

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U i

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R

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pc T

P eS o

s e rP P

el R

R u -

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mt 1

C H

l E o

on A

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d r r E

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f i R

t w u

f T

n o, h

)

t N

a1 S

5, pf F

E s

o n

n A

e U

e i

3 xt R

ve S

eu T

l r h

p 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

i A

t e

n ot n1 d

a t u T

o1 o

r cp C0 M

c et I

N S

t u U

el r

eo no o

l d

I, 1 r t

a r

A

t c

u no t

N r n a

n ot 0

uo e

a r c TC R

M 1

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7, ut M

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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 g)

AND INSTRUtlEdT NUMBER CllECK 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

li.

Flow Blased Neutron Flux-liigh S S/IM),W W (*)II),Q l

v 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')

ll21-F028 A,n,C,D) y 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 m

n e

t h

l e

w n

i i

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c i

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t o

u t

t i

)

s 1

o ts 1

p t

B i

F l

o E

e I

l' p

(

s lE t

o l

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h iF n

t t

R n

k t

d o

f c

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o e

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h fF a

r n

c R

i e

o b

w i

l E

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p a

n t

o u

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l l

t a

f l

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n 1

1 u

a c

o t

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1 f

i t

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 h

c o

p l

tn 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

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n N

n e

n s

t n

E e

p i

a 1

lt m

t e

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3 U

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l n

c bd c

R s

c a

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T u

n c

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d r y

S j

o i

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e i.

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E.

N d

s u

s i

p i

l 1

a t

y c

f s

t B

s h

n s e n

t A

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p d

o i r o

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T.

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I t

l a

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at S'

d a

s o e

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t f

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S o

a o

a d

s t

t a

i s N

t d

t s

r i

m O

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T s

a s

r ec f

C n

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h e E

o b

o n

d ch d

T c

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O l

s a

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R l l a

l u

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P l a c

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an a

t nt e

R h g e

h n

a at x

U si b

s e

hi e

I s

m g

cm C'

n l

n n

n s

e A

ow l

o g

i rn r

E i o a

i i

s ea a

R tl h

t l

u t r af s

a a

t t s

r r

n i

r bd s m b

t o

me e

i e e

i n

i st t

'H t l

e t

na t

l taa R s a

m a

ar i

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

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I En$w9'Njr T Y T

!i tt 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)

PER TRIP SYS1EH(l>)(c)

CollDITIoll Attrioll x

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 (B21-LTil-N024A-l,B-1 and w

)

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 (1121 -l'S-1101 S A,Il,C.0) a 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)

NIl 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) te 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) l 1

2 1, 2(f) 21 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; 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 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

( D12-RH-N010 A, B) g 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 1, 2, 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

{

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

St.CS Initiation (C41A-SI) 3(g)

NA 1, 2, 3 24 u

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.

TRIP FUNCTION AND INSTRlttENT NtfMBER S ICilAL(a)

PER TRIP SYSTEll(ts).M cot 3DITi oll ACT t utt n7:

5.

SiltrTIXMN C001.ING SYSTEM ISOLATi(Ni Ey 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 Wit F.

.K-

TABLE 3.3.2-2 ISOLATION AC1UATION INSTRllHENTATION SETIOlllTS ps

'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 IS01.ATION ACTUATI0li INSTRUNENTATION SETroill1S -

I i)

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

_ val.llE 2.

SECONDARY CONTAINHENT ISOLATION 9

If Reactor Building Extiaust Radiation - liigli

< 11 inr/hr

< 11 int /lir a.

(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

(C31-dFS-H603-1A, IB) e Is. Area Temperature - liigli

$ 150" F

$ 15tl" F (C31 -TS-H600A, B, C, D, E, F)

Area Ventilation Temperature A Temp - liigli

$ 50" F

$ Su" r c.

(C31-TS-N602A, B, C, D, E, F) d.

St.CS lultiation (C41A-SI)

HA NA h'

Reactor Vessel Water - 1.ow, I,evel #2

> +112 inclien

> +111 leichen e.

(B21-L1H-NO24A-1, B-1 and B21-L1H-H025A-1, B-1) _

l u

t.t.

-, ~ -

.3 TABLE 3.3.2-2 (continueil)

M c[j 11QIAf10N AGilAT1@LEt1[]URi2[ TALL.Of[_S1[P0_lj[M f

,'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)

ISCLATION SYS*'IM ?IS?ONSI T!E 7

'"?.!? ?*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 1.

I.evel #1 (B21-LT-N017A-1,B-1,C-1,D-1)

HA(,)

i:A R(g,)

r (B21-LTH-N017A-1,5-1,C-1 D-1)

D H

H 1, 2

'l 2.

Level #2 II'I (D21-LT-N024 A-1,11-1 and NA(")

NA R

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)

Og 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

1. When reactor steam pressure >500 peig.

J i

e

TABl.E 4.3.2.-1 (Continued)

IS01.ATIOtt ACTilATI0tt INSTRUMEt{TATION SilRVEII. LANCE REQUIREHEllTS usy 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 (821-LT-N024A-1,H-1 and NA NA R

mD B21-LT-H025A-1,H-1)

(H21-1.TH-N024A-1,B-1 and D

H ll I, 2, 3

B21-1.TH-N025A-1,H-1) u 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)

EIl sl.

SLCS fnitiation (C41A-SI)

NA R

liA 1, 2, 3 e

e.

Heactor Vessel Water Level -

1.ow, Level #2 NA,)

g (H21-LT-N024 A-1, B-1 and 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, I.esel #1 (B21-LT-H017A-1,B-1,C-1,D-1)

NA,)

NA R

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 uy

'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 HINIHlIH lilitillER Al'PLI CAhl.E

I 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 U

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

2 1, 2, 3 30 a

D-li.

Reactor Veunel Water f.evel - la>w, Level f3 (ll21 -I.T-flo ll A, II, C, D)

• Z 0

A A

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

1. Alaim Only.

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

u 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 2.

l.PCI HODE OF MilR SYSTEH (continued) e--

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

(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) up 1.

EllR Pump Start and LPCI Injection Valve Actisation 2

1, 2, 3, 4*,

5^

31 2.

Recirculation Loop Piump Discliarge Valve Actuation 2

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

1. Alarm only.

,0,

)

e

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

vg HIN! HUM NUNNER A PI'LI CAllt.E

,1 OPERARI.E CilAllNEl.S OPERATIONAI.

9 TRIP l1RICTIOli AllD INSTRUMENT llUHl1ER PER TRIP SYSTEM CONillH ONS ACTION q

3.

HPCI SYST131 Ni d

Reactor Vessel Water Level - Low, Level #2 a.

(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 30 H-2, C-2, D-2)

Is.

Drywell Pressure - liigli (El l-PS-fl011 A,B,C,D) 2 1,2,3 30 up c.

Conilensate Storage Tank Level-l.nw (E41 -1.S-Il002, 2**

1, 2, 3 33 E41 -I.S-IlOO 3) b N

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

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

4.

yg firywell Pressure - liigli, coincialent with a.

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

• 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

1. 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, OPERARLE CilAtiHELS -

O PERATIO'IAI.

8 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 Core Spray Puinp Discliarge Pressure - liigli (Pennissive) 2 1, 2, 3 31 c.

(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 1/ bus

.1/ bus 1, 2, 3, 4

,5 34 I;.

4.16 kv Emergency Bus y.

Undervoltage (Oegraded Voltage) 3/ bus 2/ bus 2/ bus 1, 2, 3, 4

,5 35 e.

1. Alarm only.

x E

ffRequired when ESF eqtilpnent is required to be OPERADLE.

1

[

.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 d.

Time Delay Relay 14 < t < 16 aces 14 < t < 16 secs u,

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 f,

" "* I"E

" I '"" "

"I' (Il21-Ilrs-H03l A-4, B-4, C-4, D-4) fuel gulile fuel guhle Njj c.

Reactor Vessel Shrouil I.evel 53" below t up

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

te v.

m m

TARI.E 3.3. 3-2 (continued) g M1ERCENCY CORE C001.ING SYSTEM AC'lVATION INSTRUMENTATICII SETP0lNTS Up Al.IJ RIAnl.E ti IT!IP FUtlCTION AND INSTRUllENT NUHBER TRIP SETP0lHT JAl.IIE 9

e d.

Reactor Stemen Ikime Pressure - Iow 0ll 1.

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

y 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

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

11 secouils e.

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)

,YI J

[}

E!!ERCEllCY CORE C00LINC SYSTEM ACrilATION INSTRitlENTATitW SETrollirS f';;

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

'I. IIPCI SYSTEH Reactor Vessel Water IAvel - Low, I.evel #2

> +112 inclies aliove

> +112 inctien nliove a.

(821-I.TS-NO31A-2, 11-2, C-2, D-2)

- top fuel genitle

- t up fuel gulate 1,. Drywell Pressiere - liigli (cli-Ps-nenA,B,c,0)

- 2 pelg 2 pulg 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 (Ell-PS-N010A,8,C,D)

~ 2 psig

~ 2 pulg 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

$ 120 serontin O

Core Spray Pump Dlucliarge Pressure - liigli

, 100 psig

, 1830 pnin e.

)

)

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

'A 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)

FNERGENCY COPE C001.ING SYSTEM AC1UATIOtt INSTRUMENTATIOli SETPOINTS w

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 2940 + 315 volts (Loss of Voltage)*

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 106.5 t 0.60 volts

~

u D

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 g

( R21-LT-NO31 A, B,C D)

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 in lay Relay NA R

R 1,2,3,4,5 e

c.

Hus Power Honitor (E21-KIA H)

HA R

NA 1, 2, 3, 4, 5 2.

IfCI HOIE Ol' RilR SYSTEli k

li ywell Pressure - lii gli a.

t

(

( 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 RII* )

( 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 NA *I HA R (li)

I (B21-LT-NO36; B21-1.r-NO31) 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 RII' }

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 l

( H 21 - PTil-NO2

• A-1, Il-1, C-1, D-1 )

D M

H 1, 2, 3, 4 a, sa 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

es a.

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

g

( R 21-l.T-HO 31 A, B,C, D)

NA 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 -

lit h t

( 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 HA ")

NA R(b)

I

( B 21 -l.T-NO 3 t A, B,C, D)

(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

( ll21 -1.Tti-fl042 A-1,5-1 )

D H

H s.,

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 ile 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 CllECK-CAI.l HRAT IOtt 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 h

HINIHUH NUMBER OPERABLE TRIP a:

TRIP FIR 4CTION AtlD INSTRtRENT NUMBER SYSTEMS PER ope: RATING PUHP-El 1

1.

Reactor Vessel Water level -

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 ATWS RECIRCtll.ATION PUNP TRIP SYSTEH INSTMitElfrATIOf2 SETPOINIS '

w

.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~

?:

Iit d'

i' z

a' TABI.E 4.3.6.1-1

.155 HECINClit.ATION Pt4IP TRIP SYSTEli INSTRUllENTATION SURVEll.l.ANCE REQUIREHEl(TS ps 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)

NA "

NA R(b)

I

!)

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

D H

H e

2.

Heactor Vessel Pressure 111 1 NA H

R 8

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

U s~

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.

..c o

pc.. sv. e. > :..v.e.

e.. :. ;.

.n..

n 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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, 3h Battery 1B-1 s 1089.06 a=:eres, and e

(

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.

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