ML20004F563
| ML20004F563 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/11/1981 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20004F561 | List: |
| References | |
| NUDOCS 8106190084 | |
| Download: ML20004F563 (48) | |
Text
.
CO W
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.
(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
e l
E 0
A A
c S
t r
l t
I 1
t u
i s
I' n
S e
E m
R_
e i
l i
tn las o
m i
S t
E e.
i nl T
ne u m
)
E pa d
S s n i
e eh t
u 0
)
R r n
P 9
i S
5 n
t E
7
.i n
R 1
g o
nt t
C 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 N
7 C
mc 3
O 1
(
i I
t c 3
T 6
n i
C 5
o en E.
E 7
i s o f
1 t
I nr R
U i
ot A
R
,I s
pc T
P eS o
s e rP P
el R
R u -
r e O
E sC n
T 1
oH w
mt 1
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
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
e t
7, ut M
c e ff id t
i 0
1 2
E F
1 1
1 ws h :ss p, E 4, ~
U s-Y o, >
I t
laia n y-P e
!i!lIll l
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
n n
g o
n n
c i
o s
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
e h
h iF n
t t
R n
k t
d o
f c
e m
o e
i tj s
h fF a
r n
c R
i e
o b
w i
l E
o t
e lC w
p a
n t
o u
n A.
l l
t a
f l
c h
n 1
1 u
a c
o t
)
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
o h
n N
n e
n s
t n
E e
p i
a 1
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
e i.
l l
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
e a
p d
o i r o
i 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 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
.J k
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.
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.
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
- 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.
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.
- 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
- 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
- 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.
- 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
(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.
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.
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.
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.
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
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