ML20216J497
| ML20216J497 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/16/1998 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20216J482 | List: |
| References | |
| NUDOCS 9804210398 | |
| Download: ML20216J497 (69) | |
Text
RTS Instrumentation i
3.3.1 l
Table 3.3.1 1 (pese 1 of 8)
Reactor Trip system Instrumentation l
l M MlM b APPLICA8LE NODES OR CTMER sETPotNT@
g TRIP f
sPECIFIED REQUIRED SURVEILLANCE ALLOWA8LE l
FUNCTION CONDITIOWs CMANNELs CONDIT!0Ns REQUIRENENTs VALUE 1
1.
Manuel Reactor 1,2 2
B sa 3.3.1.13 NA NA Trip 3(*), 4(*), 5(*)
2 C
sa 3.3.1.13 NA NA 2.
Power Renee Neutron Ftum e.
Nish 1,2 4
0 sa 3.3.1.1 5 111.3% RTP s 199E RTP sa 3.3.1.2 sa 3.3.1.7 sa 3.3.1.11 54 3.3.1.15 l
b.
Low 1(b) 2 4
E sa 3.3.1.1 5 27.3% RTP s 251 RTP st 3.3.1.8 sa 3.3.1.11 sa 3.3.1.15 J
l 3.
Power Renee 1,2 4
E sa 3.3.1.7 s 6.31 aTP s 1 RTP Neutron Flux High sa 3.3.1.11 with time th time Peeltive Rete cenetent constant t 2 eec 3 2 eec l
4.
Intermodlate Renee 1(b), 2(*)
2 F,G sa 3.3.1.1 5 31.11 RTP s 1 RTP I
Neutron Flum 34 3.3.1.8 sa 3.3.1.11 l
2(d) 2 N
Ta 3.3.1.1 5 31.11 RTP s 1 aTP sa 3.3.1.5 sa 3.3.1.11 (continued)
(e) With Reactor Trip Brookers (RTBs) closed and Red Centret system capable of rod withdrewel.
(b) setow the P 10 (Power Renee Neutron Flum) interlocks.
(c) Above the P 6 (Interisediate Renee Neutron Flum) interlocks.
(d) Below the P*6 (Intermodlate Renee Neutron Flum) interlocks.
(n) A channelis OPERABLE with an actual Trip Setpoint value outsde its calibratmn tolerance band provided the Trip Setpoint value is conservative with respect to ts associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
i l
l l
9804210'J98 980416 PDR ADOCK 05000424 PDR p
i Amendment No. g(
(Unit 1) 3.3-14 Vogtle Units 1 and 2 Amendment No. J (Unit 2)
)
RTS Instrumentation 3.3.1 1
Table 3.3.1 1 (pese 2 of 8)
Reactor Trip system Instrumentation NOWNE I
APPLICARLE MCSEs Ca OTHER TalP
)
l SPECIFIED REculaED suave!LLANCE ALLOWA8LE SETPolNib/
FUNCTION CON 0!TIONs CNANNELS CONDITIONS aEQUlaEMENTS VALUE 2(d) 2 1,J Sa 3.3.1.1 5 1.4 E5 5 1.0 E5 5.
source aanse sa 3.3.1.8 cas eps Neutron Flux sa 3.3.1.11 sa 3.3.1.15 l
3(83, 4(a), $(e) 2 J,K sa 3.3.1.1 s 1.4 E5 s
.0 E5 Sa 3.3.1.7 ces ces sa 3.3.1.11 sa 3.3.1.15 3('), 4('). 5(*)
1 L
sa 3.3.1.1 NA NA sa 3.3.1.11 j
l 6.
Overtemperature AT 1,2 4
E sa 3.3.1.1 Refer to aefer to j
sa 3.3.1.3 Note 1 Note 1 sa 3.3.1.6 (Pese (Pese l
sa 3.3.1.7 3.3 20) 3.3 20) sa 3.3.1.10 sa 3.3.1.15 i
l 7.
Overpower AT 1,2 4
E sa 3.3.1.1 Refer to aefer to sa 3.3.1.7 Note 2 Note 2 sa 3.3.1.10 (Pese (Pese sa 3.3.1.15 3.3 21) 3.3 21)
(continued)
(a) With aTas closed and and Control system capable of rod withdrewel.
l (d) Selow the P 6 (Interundiate sense Neutron Flum) interlocks.
In this condition, source rence Fwiction does not provide reactor trip but does provide l
l With the RT8s open.
(0) irgiut to the Nigh Flux et shutdown Alarm system (LCO 3.3.8) and indication.
l (n) A channelis OPERABLE with an actual Tnp Setpoint value outside its cabbration tolerance band provided the Trip l
Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Tnp Setpoint. A Trip Setpoint rnay be set rnore conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
r l
l
\\
t i
l Amendment No. I (Unit 1) 3.3-15 Vogtle Units I and 2 Amendment No. J# (Unit 2)
I RTS instrumentation 3.3.1 Table 3.3.1 1 (pese 3 of 8)
Reactor Trip system Instrumentation APPLICABLE MODES pggL OR OTHER SETPo!NT(d l
SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CNAn ELs CON 0!TIONs REQUIREMENTS VALUE 8.
Pressuriser Pressure
- e.. Low 10) 4 M
sa 3.3.1.1 1 1950 pais t 960(8)
I sa 3.3.1.7 pois sa 3.3.1.10 sa 3.3.1.15 l
b.
High 1,2 4
E sa 3.3.1.1 s 2395 psis s 2385 pois Sa 3.3.1.7 sa 3.3.1.10 SA 3.3.1.15 9.
Pressurizer Weter 1(f) 3 M
sa 3.3.1.1 3 93.9%
5 Level - H igh sa 3.3.1.7 sa 3.3.1.10
- 10. Reactor Coolant F low - Low j
o.
sinste Loop 1(h) 3 per N
st 3.3.1.1 2 89.41 2
isep st 3.3.1.7 I
st 3.3.1.10 i
sa 3.3.1.15 l
b.
Two Loops 1(l) 3 per M
sa 3.3.1.1 2 89.4%
t teap sa 3.3.1.7 SR 3.3.1.10 sa 3.3.1.15 (contirued)
(f) Above the P 7 (Low Power Reactor Trips Stock) interlock.
(s) Time constants utill ed in the lead los controller for Pressuriser Pressure Low are 10 seconds for lead and 1 I
second for ies.
(h) Above the P 8 (Power Renee Neutron Flum) interteck.
l i
(i) Above the P 7 (Low Power Reactor Trips Block) Interlock and below the P 8 (Power aanse Neutron Flux) interlock.
j i
(n) A channelis OPERABLE with an actual Trip Setpoint value outside its cakbration tolerance band provided the Tnp Setpoint value is conservative with respect to its associated Allowable Value and the channelis re-adjusted to within j
the estabhshed calibraten tolerance band of the Nomina! Trip Setpoint. A Trip Setpoint may be set more l
conservative than the Nominal Trip Setpoint as necessary in response to plant conditions, i
i i
Vogtle Units 1 and 2 3.3-16 Amendment No. / (Unit 1)
Amendment No. J/ (Unit 2)
RTS Instrumentation 3.3.1 i
Tebte 3.3.1 1 (pese 4 of 8)
Reactor Trip system instrumentation APPLICA8LE MODES NOWR OR OTHEn TRIP i
SPECIFIED REGulRED SURVE!LLANCE ALLOWASLE SETPOINTh/
FUNCTION CONDIT!0Ns CHANNELS CONDITIONS REGulREMENis VALUE k
- 11. Undervoltese 1(II 2 per M
sa 3.3.1.9 t 9481 Y V
RCPs bus SR 3.3.1.10 ta 3.3.1.15 l
l III 2 per M
sa 3.3.1.9 t 57.1 H2 2 7.3 H2 l
- 12. Underfrecuency I
RCPs bus sa 3.3.1.10 l
SR 3.3.1.15 13.
steen 1,2 4 per so E
sa 3.3.1.1 2 35.9%
a 37.8%
Generator (SG) st 3.3.1.7 l
Water Level - Low SA 3.3.1.10 sa 3.3.1.15 Low (centinued)
(f) Above the P 7 (Low Power Reactor Trips Stock) Interlock.
l (n) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip i
Setpoint value is conservative with respect to its associa',ed Allowable Value and the channelis re adjusted to within the established cahbration tolerance band of the Nominal Trip Setpoint. A Tnp Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
l i
1 i
l l
l 1
I I
I i
i Vogtle Units 1 and 2 3.3-17 Amendment No. I (Unit 1)
Amendment No. / (Unit 2) i I
l
I RTS Instrumentation 3.3.1 l
Table 3.3.1 1 (page 5 of 8)
Reactor Trip System Instrumentation l
l APPLICABLE MODES N
OR OTHER s
l SPECIFIED REGUlRED SURVEILLANCE ALLOWA8LE TRIP 1
l FUNCTION CON 0lTIONS CNANNELS CONDITIONS REQUIREMENTS VALUE SETPo!NTb/
l
- 14. Turbine Trip a.
Low Fluid 011 1(II 3
0 SR 3.3.1.10 2 500 pois h580pois l
Pressure SR 3.3.1.16 o
b.
Turbine Stop 1III 4
P SR 3.3.1.10 t 9duGIr
.7%
Vatw Closure SR 3.3.1.14 open open
- 15. Safety 1,2 2 trains 0
SR 3.3.1.13 NA NA Injection (SI)
Input from Engineered Safety Feature Actuation System (ESFA':)
- 16. Reector Trip System Interlocks j
l l
e.
Intermediate 2(d) 2 R
SR 3.3.1.11 b 6E 11 amp
> 1E 10 esp i
Range Neutron SR 3.3.1.12 Flux, P 6 b.
Low Power 1
1 per S
SR 3.3.1.5 NA NA Reactor Trips train Block, P 7 4
5 SR 3.3.1.11 5 50.3% RTP s 48% RTP c.
Power Range j
Neutron Flux, SR 3.3.1.12 P8 d.
Power Range 4
S SR 3.3.1.11 5 52.3% RTP 5 0% RTP Neutron Flux, 1
Power Range 4
R SR 3.3.1.11 (1,m)
(L,m)
Neutron Flux, 1s2 SR 3.3.1.12 P 10 and input to P-7 a
2 S
SR 3.3.1.10 5 12.3%
10%
l f.
Turbine lopulse 1
SR 3.3.1.12 Impulse I
tse Pressure, P-13 Pressure Pressure EcpJivalent Equivalent turbine turbine (continued)
(d) Below the P 6 (Intermediate Range Neutron Flux) Interlocks.
(hbhb (j) Above the P-9 (Power Renee Neutron Flux) Interlock.
(t) For the P-10 trput to P 7, the Attowebte value is s 12.3% RTP and the Trip Setpoint is s 10% RTP.
l or the Power Range Neutron Flux, P 10, the Alloweble Value is t 7.7% RTP and thekip Setpoint is
(::)
a 10% RTP.
(n) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Tnp Setpoint value is conservative with respect to Rs associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Tnp Setpoint may be set more conservative than the Nominal Tno Setpoint as necessary in response to plant conditions.
Vogtle Units 1 and 2 3.3-18 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
l RTS Instrumentation 3.3.1 i
febte 3.3.1 1 (pese 6 of 8)
Reactor Trip System Instrwentation APPLICABLE N00E5 g)g l
On OTHER SPECIFIED REGUIRED SURVEILLANCE ALLOWABLE TRIP (jg) a)
FUNCTION CONDITIONS CMANNELS CONDITIONS REGulREMENTS VALUE SETPolN 97 neectorgIp 1,2 2 trains T,y SR 3.3.1.4 NA NA 3 *), 4(a), $(e) 2 trains C
sa 3.3.1.4 NA NA
.ree=ers I
- 18. Reactor Trip 1,2 1 sech U,V SR 3.3.1.4 NA NA
)
I Brooker per RTs shtet Trip 3(a), 4(a), 5(*)
i each C
sa 3.3.1.4 NA NA undervoltage and Nechanisms per RTS
- 19. Automatic Trip 1,2 2 treins o,y sa 3.3.1.5 NA NA Logic 3(*I, 4(a), $(a) 2 trains C
SR 3.3.1.5 NA NA f
)
(a) With RT8s closed und Rod Control System cepeble of rod withdrawal.
(k) Including any reactor trip bypass breakers that are rocked in and closed for bypassing en RTS.
(n) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration te!erance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channelis re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservatrve than the Nominal Trip Setpoint as necessary in response to plant conditions.
1 3.3-19 Amendment No. JH!I (Unit 1)
Vogtle Units 1 and 2 Amendment No. Jt' (Unit 2)
RTS Instrumentation 3.3.1 Table 3.3.1 1 (pese 7 of 8)
Reactor Trip system Instrumentation OmiM note it oveetencerature Dette.1 The overtemperature Dette T Function Allowable value sheLL not exceed the rip Setpoint defined by the foLLowing f
e,astion by more then 2.25% of RTP.
(1 + f s) 1 100 g (1 + f s)
T
- T' - K tP -P)- f g ( AFD) i 1
4 s K, - K 3
2 (1 + t e ), (1 + f e )
s s
s L1 + f s) (1 + f s) o 2
3 Whore AT measured Loop specific RCs differential temperature, degrees F AT, indicated Loop specific RCS differentist et RTP, dooroes F l
h,3 Leed Los compensator en asesured differential temperature 1+5 s 2
time constants utillaed in Leed Les compensator for differentist temperatures vi a 8 seconds, f,,
f2 5 3 seconds f2 1
1+v3s les compensator on measured difforentist temperature time constant utill ed in Lee compensator for differential temperature, s 2 seconds f3 K
fisutementet setpoint, 51121 RTP g
i modifier for temperature, a 2.241 RTP per doeree F K2 1%1 1+fgs Leed-Les compensetor en dynamie tespersture compensetien 2 28 time constants utillaed in lead leg compensator for temperature compensations f4 f4, f a seconds, fg 5 4 seconds T
measured Loop specific RCS ewrees temperature, dooroes F 1
1+f es Les compensator en sneeured eversee temperature time constant utilized in Lee compenneter for awrese temperature, = 0 seconds f,
indicated loop specific RCS everese temperature et RTP, s $g8.4 degrees F T'
modifier for pressure, = 0.1151 RTP per pois K3 aseeured RCS pressuriser preneure, pelo P
P*
reference pressure, t 2235 pois Laplace transform verlebte, inverse seconds s
sedifier for Amlet FLLet Difference (AF9):
f,( AFD) 1.
f or AFD between *321 and +105, = 01 RTP for each 1 AFD is below 321, the trip setpoint sheLL be rechced by 3.251 RTP 2.
for each 1 AFD is above +10%, the trip setpoint sheLL be reduced by 2.7% RTP 3.
3.3-20 Amendment No. M (Unit 1)
Vogtle Units 1 and 2 Amendment No. Jr (Unit 2)
)
RTS Instrumentation 3.3.1 Table 3.3.1 1 (pese 8 of 8)
Reactor Trip System instrumentation rote 2r overcover Dette T f
l Th3 overpower Dette T Function ALLOWA8LE VALUE shall not exceed thelf rip setpoint defined by the foltouing equation I
by more then 2.85% of RTP.
g (1 + f gs) 1 (f ys) 1 1
-T" -f (AFD) s K4-Kg T
- K,T 2
100 8I Il 78I II * 'ed
, II * 'el AfoII28I II *'3 Where AT measured loop specific RCS differentist toeperature, degrees F ATo indicated toop specific RCS differentist at RTP, degrees F M3 tead-tes campensator en measured differentist temperature 1+f s 2
a 8 seconds, time constants utilf red in lead-tes compensator for differential temperature:
fi f3, f2 f s 3 secones 1
too compensator en measured dif forentist temperature 1+f as time constant utilized in too compensator for differentist temperature, s 2 secones fa K
findementet setpoint, 5109.5% RTP 4
K, eedifier for temperature chenees t 21 RTP per degree F for increening temperature, t 01 RTP per degree F for decreasing temperature
.171.
1+fys rete tes compensator on dynamic temperature compensation time constant utilized in rete tes compensator for temperature compensation, t 10 seconde fy measut*i toop specific RCS everage temperature, degrees F T
i tag coepensator on measured everage temperature 1+fes time constant utilized in too compensator for everese temperature, = 0 seconds f,
t 0.20% RTP per degree F for T > T*, = 01 RTP for i s T*
K, modifier for temperature:
Indicated toop specific RCS everage temperature et RTP, 5 588.4 degrees F T*
Leptoce transform vertebte, iriverse seconds s
modifier for Amlet Flus Olfference (AFD), = 0% RTP for ett AFD f (AFD) g i
l l
3.3-21 Amendment No. M (Unit 1)
Vogtle Units 1 and 2 Amendment No. )( (Unit 2) i
ESFAS Instrumentation 3.3.2 l
l Table 3.3.2 1 (pese 1 of 7)
Enstneered safety Feature Actuation system Instrumentation l
APPLICABLE NODES on NOMINAL l
OTHER SPECIFIED REQUIRED suave!LLANCE ALLOWABLE TRIP j
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETP0lNT e
1.
Safety injection e.
Manuet Initiation 1,2,3,4 2
8 sa 3.3.2.6 NA ILt b.
Automatic 1,2,3,4 2
C SR 3.3.2.2 NA NA Actuation Logic sa 3.3.2.3 and Actuation sa 3.3.2.5 Seteys l
c.
Containment 1,2,3 3
0 sa 3.3.2.1 s 4.4 psis 3.8 pois Pressure = Nigh 1 sa 3.3.2.4 sa 3.3.2.7 sa 3.3.2.8 d.
Pressuriser 1,2,3(e) 4 0
sa 3.3.2.1 2 1856 pois 1870 pois l
Pressure - Low sa 3.3.2.4 sa 3.3.2.7 sa 3.3.2.8 e.
steen Line 1,2,3(a) 3 per 0
sa 3.3.2.1 570(b) t 585(b)
{
Pressure Low steen sa 3.3.2.4 y ois pois p
line sa 3.3.2.7 Sa 3.3.2.8 l
(continued)
(e) Above the P 11 (Pressuriser Pressure) Interlock.
(G) Time constants used in the Leed/Les controtter are t t 50 seconds and t 5 5 seconds.
i (i) A channelis OPERABLE with an actual Trip Setpoint value outsKie its calibration tolerance band provided the Trip Setpoint value is conservatwo with respect to its associated Allowable Value and the channelis re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservatue than the Nominal Trip Setpoint as necessary in response to plant conditions.
l l
l AmendmentNo.I(
(Unit 1)
Vogtle Units 1 and 2 3.3-30 Amendment No. J (Unit 2) l
1 ESFAS Instrumentation 3.3.2 l
tacte 3.3.2 1 (pese 2 of 7)
Eneirwered safety Feature Actuation system Instrumentation N0Mit4AL l
APPLICA8LE amts oa OTMER SPECIFIED REQUIRED SURVEILLANCE ALLOWASLE TRIP l
$ETPolNT($
FUNCTION CONDITIONS CHAhmELS CONDITION $
REQUIRENENTS VALUE 2.
Contairement spray a.
Manuel Initiation 1,2,3,4 2
s 52 3.3.2.6 NA NA b.
Automatic 1,2,3,4 2
C sa 3.3.2.2 NA NA Actuation Logic sa 3.3.2.3 sa 3.3.2.5 and Actuation J
.ei.ys c.
Conteirunent Pressure High - 3 1,2,3 4
E sa 3.3.2.1 5 22.4 pais 21.5 psis l
Sa 3.3.2.4 sa 3.3.2.7 Sa 3.3.2.8 l
(continued)
(i) A channelis OPERABLE with an actual Tnp Setpoint value outside ks calibration tolerance band provided the Iop Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
l l
3.3-31 Amendment No. 96 (Unit 1) l Vogtle Units 1 and 2 Amendment No. 74 (Unit 2) i
ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (pose 3 of 7)
Engineered safety Feature Actuetton system Instruisentation APPLICAsLE yysa
$PECIFIED REQUIRED
$URVEILLANCE ALLOWAsLE TRIP
\\
FUNCTION CONDITIONS CMANNELS CONDITIONS REQUIREMENTS VALUE SETPOIN J 3.
Phase A conteirinent Isoietion (e) nenuel Initletion 1,2,3,4 2
e sa 3.3.2.6 NA NA (b) Automatic 1,2,3,4 2 trains C
sa 3.3.2.2 NA NA Actuation Logic st 3.3.2.3 sa 3.3.2.5 and Actuation Relays (c) safety injection Refer to F a tion 1 (sofety injection) for all initiation f ations and rewirements.
4 Steen Line Isolation e.
meruel Initiation 1,2(8) 3(8) 2 F
sa 3.3.2.6 NA NA b.
Automatic 1,2(8) 3(C) 2 G
sa 3.3.2.2 NA NA Actuation Logic sa 3.3.2.3 and Actuation sa 3.3.2.5 Relays (contirued)
Except when one esin steem isolation velve eruf associated bypass isolation valve per stees ilne is closed.
(c)
(i) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservatrve with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Tnp Setpoint as necessary in response to plant cond:tions.
3.3-32 Amendment No. 96 (Unit 1)
Vogtle Units 1 and 2 Amendment No. 74 (Unit 2)
)
\\
t ESFAS Instrumentation l
3.3.2 l
f Table 3.3.2 1 (pese 4 of 7)
Engineered Safety Feature Actuation System instrumentation
{
i APPLICABLE f
THER SETPOINT(P/,- )
l TalP SPECIFIED REQUIRED
$URVEILLANCE ALLOUA8LE l
FUNCT10N CONDITIONS CHANNELS CONDITIONS REQUlaEMENTS VALUE 4.
Steam Line Isolation (continued) c.
Contelruent 1,2(C3, 3
0 st 3.3.2.1 s 15.4 pais 5 14.5 psig k;
sa 3.3.2.4 l
Pressure - Migh 2 3(c) sa 3.3.2.7 Sa 3.3.2.8 d.
Steam Line j
Pressure (1) Low 1,2(83, 3 per 0
sa 3.3.2.1 3 570 (b) 1 585 (b)
{
steam SR 3.3.2.4 psis psis 3(e)(c) line sa 3.3.2.7 j
sa 3.3.2.5 (2) Negative 3(dI(*)
3 per o
sa 3.3.2.1 s 125 (*)
s 100 (*)
l
)
1 Rete - N igh ateen ta 3.3.2.4 psi /see i/see Line sa 3.3.2.7 sa 3.3.2.8 l
i (cantinuso)
(e) Above the P 11 (Pressurizer Pressure) interlock.
s 5 seconds.
(b) Time constants used in the Leed/Les controtter are t, t 50 seconds and t2 (c) Except when one mein steam isolation velve and associated bypass isolation volve per steen line is closed.
(d) Below the P 11 (Pressurl er Pressure) interlock.
(e) Time constant utilf red in the rate /les controtter is a 50 seconds.
A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip (i)
Setpoint value is conservative with respect to its associated Allowabte Value and the channelis re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
3.3-33 Amendment No. 96 (Unit 1)
Vogtle Units 1 and 2 Amendment No. 74 (Unit 2) l l
ESFAS Instrumentation 3.3.2 table 3.3.2 1 (page 5 of 7)
Engineered safety Feature Actuation system Instrumentation l
C APPLICA$LE gogggL l
NmEs on CTNEa sETPo!N[Tv-}l TRIP sPECIFIED REQUtaED suavEILLANCE ALLOWASLE FUNCTION CON 0!TIONs CNANNELs CONDITIONS REQUIREMENTS VALUE e
l 5.
Turbine Trip and Feechseter isolation l
e.
Automatic 1,2(II 2 trains H
sa 3.3.2.2 NA NA l
Actuation Logic sa 3.3.2.3 l
arms Actuation sa 3.3.2.5
(
Relays l
l b.
Low aCs Teve 1,2(II 4
I sa 3.3.2.1 2 541.5 'F 564 'F SR 3.3.2.4 sa 3.3.2.7 Coincident with Refer to Function Se for ett P 4 requirements.
aeector trip, P 4 c.
SG Water 1,2(f) 4 per sc I
sa 3.3.2.1 s 87.9%
s
.01 Level - High High sa 3.3.2.4 (P 14) sa 3.3.2.7 sa ?.3.2.8 d.
Safety injection Refer ;o F metion 1 (Safety injection) for all initletion l
f mctions and requirements.
6.
Auxillery Feedwater a.
Automa tic 1,2,3 2 trains G
sa 3.3.2.2 NA NA Actuation Logic sa 3.3.2.3 and Actuation sa 3.3.2.5 Releys b.
sc Water 1,2,3 4 per SG D
sa 3.3.2.1 2 35.9%
7.8%
Level - Low Low sa 3.3.2.4 SR 3.3.2.7 l
sa 3.3.2.8 (continued) i l
(f) Except d en one MFly or MFav. and its essecleted bypees volve per feedwater line is closed and deactivated l
or isolated int a closed menuel vetve.
l (i) A channelis OPERABLE with an actual Trip Setooint value outside its cabbration tolerance band provided the Trip t
l Setpcint value is conservative with respect to its ossociated Allowable Value and the channelis re-adjusted to within l
the established cahbration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant condrJons.
Vogtle Units 1 and 2 3.3-34 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
l ESFAS Instrumentation 3.3.2 i
Table 3.3.2 1 (pese 6 of 7)
Engineered saf ety Feature Actuation System Instrumentation APPLICA8LE
$fNER
- 0 Min l
f SPECIFIED REQUIRED SURVEILLANCE ALLOWA8LE TRIP /)
g FUNCTION CON 0!TIONS CNANNELS CONo!TIONS REQUIREMENTS VALUE SETPOINQ4,1
(
i 6.
Auxiliary Feedwater (continued) c.
Safety injection Refer to F m etion 1 (sofety injection) for ett initiation.
f fmctions and regJirements.
I d.
Trip of att Main 1,2(83 1 per J
sa 3.3.2.6 NA NA Feeshester Puigas pump 7.
semi outomatie switchover to Contetruusnt Sg e.
Automatic 1,2,3,4(h) 2 C
st 3.3.2.2 NA NA Actuation Logic
$4 3.3.2.3 and Actuation SR 3.3.2.5 Retsys b.
Refueline Water 1,2,3,4 4
K sa 3.3.2.1 1 264.9 in.
t 275.3 in.
Storage Tank 34 3.3.2.4 sa 3.3.2.7 (RW5T) Level - Low SR 3.3.2.8 Law Coincident with Refer to Fmetion 1 (Safety injection) for ett initiation safety injection feetions and reeJirements.
tcentinued)
(g) When the Main f eedwater System is operatin0 to supply the SGs.
In MG)E 4, only 1 train is required to be OPERABLE to sweert semi automatic switchover for the RNA pump (h) that is regJired to be OPERABLE in accordence with specification 3.5.3, ECCS shutdown.
(i) A channelis OPERABLE wrth an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channelis re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
I l
3 3-35 Amendment No. 96 (Unit 1)
Vogtle Units 1 and 2 Amendment No. 74 (Unit 2)
E
r ESFAS Instrumentation 3.3.2 i
l febte 3.3.2 1 (pese 7 of 7)
En0ineered Safety f eature Actuation System Instrumentation l
APPL!CASLE fMER TRIP SPECIFIED REQUIRED SURVEILLANCE ALLOWA8LE SETPOINh f
FUNCTION CONDIT!0NS CHANNELS CONDITIONS REGUIREMENTS VALUE
- 8. ESFAS Interlocks l
- a. Reector Trip, P 4 1,2,3 1 per F
sa 3.3.2.9 NA NA train, 2 trains
- b. Pressuriser Pressure, 1,2,3 3
L sa 3.3.2.4 s 2010 psie 2000 psis P 11 sa 3.3.2.7 (1) A channelis OPERABLE with an actual Tnp Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its assocated Allowable Value and the channelis re-adjusted to within the established calibraten tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoir't as necessary in response to plant conditions.
l i
Vogtle Units 1 and 2 3.3-36 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2) a-
RTS Instrumentation B 303.1 BASES BACKGROUND Sianal Process Control and Protection System (continued) the other channels providing the protection function actuation. Again, a single failure will neither cause nor prevent the protection function actuation.
These requirements are described in.tEEE-279-1971 (Ref. 4).
The actual number of channels required for each unit parameter is specified in Reference 1.
Two logic channels are required to ensure no single random failure of a logic channel will disable the RTS.
The logic channels are designed such that testing required while the reactor is at power may be accomplished without causing trip.
Provisions to allow removing logic channels from service during maintenance are unnecessary because of the logic system's designed reliability.
Trio Setooints and Allowable Values The Trip Setpoints are the nominal values at which the bistables are set. Any bistable is considered to be properly adjusted when the "as left" value is within the band for CHANNEL CALIBRATION eaemaasy The Trip Setpoints used in t b
abl s are based on the an.lytical. limits stated in Reference 1.
The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. To allow for calibration tolerances, instrumentation uncertainties, instrument drift, and severe environment errors for those RTS channels that must function in harsh environments as defined by 10 CFR 50.49 (Ref. 5),
the Trip Setpoints and Allowable Values specified in Table 3.3.1-1 in-the accompanying LCO are conservatively adjusted with respect to the analytical limits. A detailed description of the methodology used to calculate the Trip Setpoints, including their explicit uncertainties, is.
rovided in the "RTS/ESFAS Setpoint Methodology Study" p(Ref. 6). The actual nominal Trip Setpoint entered into the bistable is more conservative than that specified by the Allowable Value to account for changes in random measurement errors detectable by a COT. One example of such a change in measurement error is drift during the surveillance interval.
(continued)
B 3.3-4 Revision No. 0 Vogtle Units 1 and 2
RTS Instrumsntation B 3.3.1 BASES
~
BACKGROUND Trio Setooints and Allowable Values (continued)
If the measured setpoint does not exceed the Allowable Value, the bistable is considered OPERABLE.
Setpoints in accordance with the Allowable Value ensure that SLs are not violated during A00s (and that the consequences of DBAs will be acceptable, providing the unit is operated from within the LCOs at the onset of the A00 or DBA and the equipment functions as designed). ;Me tht " +ka i
TeMe 3.3 &l-ge /g 4:r;=3 ai; LCO 3.3.1, the Ti ip 3c6puinn vi
___S.
+-
Each channel of the process control equipment can be tested on line to verify that the signal or setpoint accuracy is within the specified allowance requirements of Reference 2.
Once a designated channel is taken out of service for testing, a simulated signal is injected in place of the i
field instrument signal. The process equipment for the channel in test is then tested, verified, and calibrated.
SRs for the channels are specified in the SRs section.
The Trip Setpoints and Allowable Values listed in Table 3.3.1-1 are based on the methodology described in Reference 6, which incorporates all of the known uncertainties applicable for each channel. The magnitudes of these uncertainties are factored into the detennination of each Trip Setpoint. All field sensors and signal processing equipment for these channels are assumed to operate within the allowances of these uncertainty magnitudes.
Solid State Protection System The SSPS equipment is used for the decision logic processing of outputs from the signal processing equipment bistables.
To meet the redundancy requirements, two trains of SSPS, each performing the same functions, are provided.
If one train is taken out of service for maintenance or test purposes, the second train will provide reactor trip and/or ESF actuation for the unit.
If both trains are taken out of service or placed in test, a reactor trip will result.
Each train is packaged in its own cabinet for physical and electrical separation to satisfy separation and independence (continued)
Vogtle Units 1 and 2 B 3.3-5 Revision No. O
l INSERT FOR BASES PAGE B 3.3-5 For the purpose of demonstrating compliance with 10 CFR 50.36 to the extent that the Technical Specifications are required to specify Limiting Safety System Settings (LSSS),
the LSSS for VEGP are comprised of both the Nominal Trip Setpoints and the Allowable Values specified in Table 3.3.1-1. The Nominal Trip Setpoint is the expected value to be achieved during calibrations. The Nominal Trip Setpoint considers all factors which may affect channel performance by statistically combining rack drift, rack measurement and test equipment effects, rack calibration accuracy, rack comparator setting accuracy, rack l
temperature effects, sensor measurement and test equipment effects, sensor calibration I
accuracy, primary element accuracy, and process measurement accuracy. The Nominal j
Trip Setpoint is the value that will always ensure that safety analysis limits are met (with margin) given all of the above effects. The Allowable Value has been established by considering the values assumed for rack effects only. The Allowable Value serves as an operability limit for the purpose of the quarterly CHANNEL OPERATIONAL TESTS.
l l
l r
RTS Instrumentation B 3.3.1 BASES i
BACKGROUND Reactor Trio Switchaear (continued) trip mechanism is sufficient by itself, thus providing a diverse trip mechanism.
The decision logic matrix functions are described in the functional diagrams included in Reference 1.
In addition to the reactor trip or ESF, these diagrams also describe the various " permissive interlocks" that are associated with unit conditions.
Each train has a built in testing device that can automatically test the decision logic matrix 1
Functions and the actuation devices while the unit is at power.
When any one train is taken out of service for testing, the other train is capable of providing unit monitoring and protection until the testing has been completed.
The testing device is semiautomatic to minimize testing time.
APPLICABLE ~
The RTS functions to maintain the SLs during all A00s and SAFETY ANALYSES, mitigates the consequences of DBAs in all MODES in LCO, and LCO, and dich the RTBs are closed.
APPLICABILITY l
Each of the analyzed accidents and transients can be detected by one or more RTS Functions.
The accident analysis described in Reference 3 takes credit for most RTS trip Functions.
RTS trip Functions not specifically credited in the accident analysis are qualitatively credited in the safety analysis and the NRC staff approved licensing basis for the unit. These RTS trip Functions may provide protection for conditions that do not require dynamic transient analysis to demonstrate Function performance.
They may also serve as backups to RTS trip Functions that were credited in the accident analysis.
The LC0 requires all instrumentation performing an RTS Function, listed in Table 3.3.1-1 in the accompanying LCO, to be OPERABLE.
Failure of any instrument renders the affected channel (s) inoperable and reduces the reliability of the affected Functions. 4 lhh
~
The LCO generally requires OPERABILITY of four or three channels in each instrumentation Function, two channels of Manual Reactor Trip in each logic Function, and two trains in each Automatic Trip Logic Function.
Four OPERABLE (continued)
Vogtle Units 1 and 2 8 3.3-7 Revision No. O
l l
l INSERT FOR BASES PAGE B 3.3-7 The Nominal Trip Setpoint column is modified by a Note that requires the as-left l
condition for a channel to be within the calibration tolerance for that channel. In l
addition, the as-left condition may be more conservative than the specified Nominal Trip Setpoint. The conservative direction is established by the direction of the inequality I
applied to the Allowable Value. It is consistent with the setpoint methodology for the as-left trip setpoint to be outside the calibration tolerance but in the conservative direction with respect to the Nominal Trip Setpoint. For example, the Power Range Neutron Flux l.
High trip setpoint may be set to a value less than 109% during initial startup following a l
refueling outage until n sufficiently high reactor power is achieved so that the power l
range channels may be calibrated. In addition, certain Required Actions may require that the Power Range Neutron Flux High trip setpoints and/or the Overpower Delta-T setpoints be reduced based on plant conditions.
l l
l i
I
i RTS Instrumentation
{
B 3.3.1 BASES APPLICABLE 6.
Overtemocrature AT (continued)
SAFETY ANALYSES, LCO, and This results in a two-out-of-four trip logic.
Section APPLICABILITY 7.2.2.3 of Reference 1 discusses control and protection system interactions for this function. Note that this Function also provides a signal to generate a turbine runback prior to reaching the Trip Setpoint.
A turbine runback will reduce turbine power and reactor power.
A reduction in power will normally alleviate the Overtemperature AT condition and may prevent a rwactor trip.
Delta-T, as used in the overtemperature and overpower o
AT trips, represents the 100% RTP value as measured for each loop.
This normalizes each locp's AT trips to the actual operating conditions existing at the time of measurement, thus forcing the trip to reflect the equivalent full power conditions as assumed in the accident analyses.
These differences in RCS loop AT can be due to several factors, e.g., differences in RCS loop flows and slightly asyisetric power distributions between quadrants.
While RCS loop flows are not expected to change with cycle life, radial power redistribution between quadrants may occur, resulting in small changes in loop specific AT values.
Therefore, loop specific AT, values are measured as needed to ensure they represent actual core conditions.
The LCO requires all four channels of the
/A/Jid Y Overtemperature AT trip Function to be OPERABLE.. Note y
that the Overtemperature AT Function receives input U
from channels shared with other RTS Functions.
Failures that affect multiple Functions require entry into the Conditions applicable to all affected Functions.
In MODE 1 or 2, the Overtemperature AT trip must be OPERABLE to prevent DNB.
In MODE 3, 4, 5, or 6, this j
trip Function does not have to be OPERABLE because the reactor is not operating ano there is insufficient heat production to be concerned about DNB.
1 i
(continued)
{
Vogtle Units 1 and 2 B 3.3-16 Revision No. O I
l
)
l INSERT FOR BASES PAGE B 3.3-16 l
The parameter K is the principal setpoint gain, since it defines the function offset. The i
l parameters K and K define the temperature gain and press.ure gain, respectively. The 2
3 j
values for T' and P' are key reference parameters corresponding directly to plant safety l
analyses initial conditions assumptions for the Overtemperature AT function. For the purposes of performing a CHANNEL CALIBRATION, the values for K, K, K, T', and i
2 3
P' are utilized in the safety analyses without explicit tolerances, but should be considered as nominal values for instrument settings. That is, while an exact setting is not expected, a setting as close as reasonably possible is desired. Note that for T', the value for the hottest RCS loop will be set as close as possible to 588.4 F. The value oft' for the remaining RCS loops will be set appropriately less than 588.4 *F based on the actual loop l
specific indicated T.,. The engineering scaling calculations use each of the referenced parameters as an exact gain or reference value. Tolerances are not applied to the individual gain or reference parameters. Tolerances are applied to each calibration module and the overall string calibration. In order to ensure that the Overtemperature AT l
setpoint is consistent with the assumptions of the safety analyses, it is necessary to verify l
during the CHANNEL OPERATIONAL TEST that the Overtemperature AT setpoint is l
within the appropriate calibration tolerances for the defined calibration conditions (Ref.
I 9).
i l
i l
f l
L
1 RTS Instrumentation B 3.3.1 BASES i
APPLICABLE 7.
Overnower 6T (continued)
SAFETY ANALYSES, LCO, and Delta-T, as used in the overtemperature and overpower o
APPLICABILITY AT trips, represents the 100% RTP value as measured for each loop.
This nomalizes each loop's AT trips to the actual operating conditions existing at the time of measurement, thus forcing the trip to reflect the equivalent full power conditions as assumed in the accident analyses. These differences in RCS loop AT can be due to several factors, e.g., difference in RCS
{
loop. flows and slightly asymmetric power distributions i
between quadrants. While RCS loop flows are not expected to change with cycle life, radial power redistribution between quadrants may occur, resulting in small changes in loop specific AT values.
Therefore, loop specific AT values are measured as needed to ensure they repre,sent actual core conditions.
The LC0 requires four channele of the Overpcwer AT
- /#546 trip Function to be OPERA 8LE.t Note that the Overpower AT trip Function receives input frc:a channels shared A/M with other RTS Functions.
Failures that affect multiple Functions require entry into t.he Conditions applicable to all affected Functions.
In HDDE 1 or 2, the Overpower AT trip Function must be OPERABLE.
These are the only times that enough heat 1s generated in the fuel to be concerned about the heat generation rates and overheating of the fuel.
In MODE 3, 4, 5, or 6, this trip Function does not have to be OPERABLE Lecause the reactor is not operating and there is insufficient heat production to be concerned about fuel overheating and fuel damage.
8.
Pressurizer Pressure The same sensors (PI-0455A, B, & C PI-0456, PI-0456A, PT-0457. PI-0457A. PI-0458, PI-0458A) provide input to the Pressurizer Pressure - High and - Low trips and the Overtemperature AT trip.
Since the Pressurizer Pressure channels are also used to provide input to the Pressurizer Pressure Control System, the actuation logic must be able to withstand an input failure to (continued) vogtle Units 1 and 2 8 3.3-18 Revision No. O
INSERT FOR BASES PAGE B 3.3-18 The value for T" is a key reference parameter corresponding directly to plant safety analyses initial conditions assumptions for the Overpower AT function. For the purposes of performing a CHANNEL CALIBRATION, the values for K., K, K, and T" are 3
6 utilized in the safety analyses without explicit tolerances, but should be considered as nominal values for instrument settings. That is, while an exact setting is not expected, a setting as close as reasonably possible is desired. Note that for T", the value for the I
hottest RCS loop will be set as close as possible to 588.4 F. The value of T" for the remaining RCS loops will be set appropriately less than 588.4 F based on the actual loop specific indicated T,. The engineering scaling calculations use each of the referenced parameters as an exact gain or reference value. Tolerances are not applied to the individual gain or reference parameters. Tolerances are applied to each calibration module and the overall string calibration. In order to ensure that the Overpower AT setpoint is consistent with the assumptions of the safety analyses, it is necessary to verify during the CHANNEL OPERATIONAL TEST that the Overpower AT setpoint is within the appropriate calibration tolerances for defined calibration conditions (Ref. 9). Note that for the parameter K, in the case of decreasing temperature, the gain setting must be 2 3
0 to prevent generating setpoint margin on decreasing temperature rates. Similarly, the setting for K. is required to be equal to 0 for conditions where T s T".
s
RTS Instrumentation B 3.3.1 BASES l
REFERENCES 2.
FSAR, Chapter 6.
(continued) 3.
FSAR, Chapter 15.
4.
S.
l 6.
WCAP-11269, Westinghouse Setpoint Methodology for i
Protection Systemsj AS supple.m44td b :
7 lblSLRT
=
7.
WCAP-10271-P-A, Supplement 2, Rev. 1, June 1990.
8.
FSAR, Chapter 16.
9 k%Aouse ldhr GP-lG&9&,Nnwher4, I997 I
i l
l l
l l
Vogtle Units 1 and 2 B 3.3-60 Revision No. 0
i l
INSERT FOR BASES PAGE B 3.3-60 Amendments 34 (Unit 1) and 14 (Unit 2), RTS Steam Generator Water Level -Low Low, ESFAS Turbine Trip and Feedwater Isolation SG Water Level - High High, and ESFAS AFW SG water Level - Low Low.
l l
Amendments 48 and 49 (Unit 1) and Amendments 27 and 28 (Unit 2), deletion of RTS l
Power Range Neutron Flux High Negative Rate Trip.
Amendments 60 (Unit 1) and 39 (Unit 2), RTS Overtemperature AT setpoint revision.
l Amendments 57 (Unit 1) and 36 (Unit 2), RTS Overtemperature and Overpower AT time constants and Overtemperature AT setpoint.
Amendments 43 and 44(Uniti) and 23 and 24 (Unit 2), revised Overtemperature and Overpower AT trip setpoints and allowable values.
I l
1 r
i l
l
1 ESFAS Ins?,rumentation B 3.3.2 4
l BASES BACKGROUND Sianal Processina Eauioment (continued)
Generally, if a parameter is used for input to the SSPS and a control function, four channels with a two-out-of-four logic are sufficient-to provide the required reliability and redundancy. The circuit must be able to withstand both an input failure to the control system, which may then require the protection function actuation, and a single failure in the other channels providing the protection function actuation. Again, a single failure will neither cause nor prevent the protection function actuation.
These requirements are described in IEEE-279-1971 (Ref. 4).
The actual number of channels required for each unit parameter is specified in Reference 2.
Trio Setooints and Allowable Values The Trip Setpoints are the nominal values at which the bistables are set. Any bistable is considered to be properly adjusted when the "as left" value is within the i
band for CHANNEL CALIBRATION 2 r n,.
l}olkrQMCL The Trip Setpoints used in the bistables are based on the analytical limits stated in Reference 2.
The selection of these Trip. Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. To allow for calibration tolerances, instrumentation uncertainties, instrument drift, and severe environnient errors for those ESFAS channels that must function in harsh environments as defined by 10 CFR 50.49 (Ref. 5), the Trip Setpoints and Allowable -Values specified in Table 3.3.2-1 in the accompanying LCO are conservatively' adjusted with respect to the analytical limits.
d.n.-: A L.,..'.:..
Sf 9;y =;d..
k M ; :h; Trf; w i n......w.
.:..;i;;, i:
Rt;;i.t;, :..,.l...,3 um ii r iI:d ' tt; 17,T,,i 0.;,,;,...
- ',.;h;2 %;i "a wur 7.;f.5). The actual nominal Trip Setpoint entered into the bistable is more conservative than that specified by the Allowable Value to account for changes in random measurement errors detectable by.a COT. One example of such a change in measurement error is drift during the surveillance interval.
If the measured setpoint does not exceed the Allowable value, the bistable is considered OPERABLE.
(continued)
B 3.3-63 Revision No. 0 Vogtle Units 1 and 2
ESFAS Instrumentation B 3.3.2 i
BASES BACKGROUND Seauencer Outout Relavs (continued) sequencer and are part of the control circuitry of these ESF loads.
There are two independent trains of sequencers and each is powered by the respective train of 120-Vac ESF electrical power supply.
The power supply for the output relays is the sequencer power supply.
The applicable output relays are tested in the slave relay testing procedures, and l
in particular, in conjunction with the specific slave relay also required to actuate to energize the applicable ESF l
load.
APPLICABLE Each of the analyzed accidents can be detected by one or SAFETY ANALYSES, more ESFAS Functions. One of the ESFAS Functions is the l
LCO, AND primary actuation signal for that accident.
An ESFAS APPLICABILITY Function may be the primary actuation signal for more than one type of accident. An ESFAS Function may also be a secondary, or backup, actuation signal for one or more other l
accidents.
For example, Pressurizer Pressure - Low is a rimary actuation signal for small loss of coolant accidents LOCAs) and a backup actuation signal for steam line breaks SLBs) outside containment.
Functions such as manual initiation, not specifically credited in the accident safety ana?ysis, are qualitatively credited in the safety analysis and the NRC staff approved licensing basis for the unit.
These Functions may provide protect on for conditions that do not require dynamic transient analysis to demonstrate Function performance. These Functions may also serve as backups to Functions that were credited in the accident analysis (Ref. 3).
The LCO requires all instrumentation performing an ESFAS Function to be OPERABLE.
Failure of any instrument renders the affected channel (s) inoperable and reduces the reliabilityoftheaffectedFunctions.f The LCO generally requires OPERABILITY of four or three channels in each instrumentation function and two channels in each logic and manual initiation function.
The two-out-of-three and the two-out-of-four configurations allow one channel to be tripped during maintenance or l
testing without causing an ESFAS initiation.
If an instrument channel is equipped with installed bypass capability, such that no jumpers or lifted leads are (continued) j B 3.3-66 Revision No. O Vogtle Units 1 and 2
r 4
INSERT FOR BASES PAGE B 3.3-66 The Nominal Trip Setpoint column is modified by a Note that requires the as-left condition for a channel to be within the calibration tolerance for that channel. In addition, the as-left condition maybe more conservative than the specified Nominal Trip Setpoint. The conservative direction is established by the direction of the inequality applied to the Allowable Value. It is consistent with the setpoint methodology for the as-left trip setpoint to ' ' outside the calibration tolerance but in the conservative direction with respect to the h.
ial Trip Setpoint.
l l
l l
l I
I l
ESFAS Instrumentation j
B 3.3.2 BASES SURVEILLANCE SR 3.3.2.8 (continued)
)
REQUIREMENTS verification of these devices every 18 months.
The 18 month Frequency is consistent with the typical refueling cycle and is based on unit operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.
This SR is modified by a Note that clarifies that the turbine driven AFW pump is tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 900 psig in the SGs.
l SR 3.3.2.9 SR 3.3.2.9 is the perfomance of a TADOT as described in SR 3.3.2.6 for the P-4 Reactor Trip Interlock, and the Frequency is once per 18 months.
This Frequency is based on operating experience. The SR is modified by a note that excludes verification of setpoints during the TADOT.
The function tested has no associated setpoint.
REFERENCES 1.
FSAR, Chapter 6.
2.
FSAR, Chapter 7.
3.
FSAR, Chapter 15.
4.
5.
6.
WCAP-11269. Westinghouse Setpoint Metaodology for Protection Systemsj 0) Supp lemeAfe4 by:
u ERT n
=
7.
WCAP-10271-P-A, Supplement 2, Rev. 1, June 1990.
8.
FSAR, Chapter 16.
9.
WfN//Mb'0MC $$4V # /CHC. Alors.,&s,1992 J
vogtle Units 1 and 2 8 3.3-109 Revision No. O
I l'. a. Nucicer Regulatory Commission LCV-1102-B.
)
Page 2 j
Based on discussion with the NRC staff on January 28,1998, SNC proposes to revise new footnotes "n" and "i" to read as follows:
"A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its i
associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions."
This revision to our original submittal addresses NRC staff concerns that the as-len value for a trip setpoint be within the calibration tolerance around the nominal value, unless plant conditions require that the trip setpoint be left more conservative than the value specified in the Nominal Trip Setpoint column of Tables 3.3.1-1 or 3.3.2-1.
I Appropriate Bases changes (inserts for Bases pages B 3.3-7 and B 3.3-66) are included to address the revisions to new footnotes "n" and "i".
LCV-1102 proposed deleting the inequality and equality mathematical operators that are presently applied to the gain and reference values for overtemperature and i
overpower AT (K,, K,, K,, K., K,, K., T', T", and P') as they appear in Notes 1 and 2 to Table 3.3.1-1. Bases inserts to pages B 3.3-16 and B 3.3-18 were provided which were intended to support the treatment of the gain and reference values for the overtemperature and overpower AT functions as " nominal" values. During a telephone conversation on March 26,1998, the NRC staff stated that our method for implementing the gain and reference values during a channel calibration appears to be an acceptable and conservative approach, and that they agree with the treatment of the overtemperature and overpower AT setpoints (as generated by the equations) as nominal values. On this basis, and the fact that the proposed change has generic implications for Westinghouse plants equipped with similar hardware as VEGP, the staff recommended that we not propose to delete the referenced inequality and equality mathematical operators for the overtemperature and overpower AT gain and reference values at this time. The staff will consider a potential generic change to l
the standard TS. On the strength that the staff finds our approach to implementing these gain and reference values to be an acceptable method of complying with the TS requirements, SNC is revising our proposed change to the Table 3.3.1-1 such that we are no longer proposing to delete the inequalities applied to the gain and reference values for overtemperature and overpower AT. Bases inserts for pages B 3.3-16 and B 3.3-18 which explain our method ofimplementing the gain and i
reference values are included with this submittal in accordance with our discussions l
with the staff, A new Bases insert for page B 3.3-5 is included with this submittal to address NRC e
staff concerns with the specification of the Limiting Safety System Settings (LSSS) in accordance with 10 CFR 50.36.
I
, U..S.' Nuclear Regulatory Commission i
LCV-1102-B Page 3 This submittal revises the Bases references for LCOs 3.3.1 and 3.3.2 to include a complete set of references for setpoint methodologies. A duplicative reference to the i
setpoint methodology is deleted from page B 3.3-63.
I Pages B 3.3-4 and B 3.3-63 are revised by changing the word " accuracy" to e
" tolerance" in the first paragraph under the heading " Trip Setpoints and Allowable Values." This change makes the Bases consistent with new footnotes "n" and "i",
and is consistent with the setpoint methodology.
The NRC staff requested that SNC provide a copy of new Reference 9 for Bases inserts for pages B 3.3-16 and B 3.3-18. The document is proprietary to Westinghouse. Therefore, the appropriate documentation to transmit this information pursuant to 10 CFR 2.790 is enclosed and supports a request for withholding from public disclosure.
At the time of our January 28,1998 meeting, it was our intention and that of the staffs to discuss a second set of questions from the NRC staff. Ilowever, the reviewer whose
]
questions we intended to discuss was unavailable at that time. For the record, the questions and our response are reproduced here.
1.
You state that the Allowable Value for Table 3.3.1-1, Function 14.b, Turbine Trip -
Turbine Stop Valve Closure, are proposed to be revised from "2 96.7% open" to "2 90%
open." Footnotes I and m of Table 3.3.1 1 are proposed to be revised to refer to the j
" Nominal Trip Setpoint" and delete the inequalities applied to the trip setpoints.
]
Describe the method of detecting the percent closure of the turbine stop valve using a.
the valve-mounted limit switches. What type of position indicators are on valve stems? You state that the valves are either fully open or fully closed. How fast is the closure time? What is the method for valve closure?
A limit switch is mounted on the valve yoke, in proximity to each valve's stem.
The limit switch is near the top of the stem travel and is normally held in j
position while the valve is open. When the valve closes, the stem-mounted arm moves down with the stem and releases the switch to move to its actuated position. The change in switch contact position is input to a 4 out of 4 logic circuit in SSPS. The closure of 4 out of 4 turbine stop valves represents a turbine trip, thus when this logic is satisfied, SSPS generates an anticipatory reactor trip.
The turbine stop valves are not designed for modulating service (as opposed to the turbine control valves). The stop valves are fully open when the turbine is in operation and are fully closed when the turbine is tripped. When the turbine is
r.
U.MNuclear Regulatory Commission LCV-1102-B
? age 4 tripped, the stop valves close nearly instantaneously (less than I second). With this very brief closure time, the potential impact of the proposed change of allowable value is a delay in this trip on the order of milliseconds.
The stop valves are held open against spring force by hydraulic pressure supplied by the turbine EllC system. When the turbine trips, hydraulic fluid is released from the stop valve actuators, and the valves are closed by the j
unopposed spring force.
l I
b.
In Table 3.3.1-1, Function 14.b, for Turbine Stop Valve Closure, there is a "P" under j
the condition column. What does this stand for?
The letter "P" refers to the applicable Condition of the LCO.
e c.
Discuss further your use of" Nominal Trip Setpoint." How do you decide what to set for this value? What are the safety issues related to how accurate this value is set to?
A calculation was performed to determine the NTS provided. It is based on the physical layout of the limit switch assembly on the valve.
Since the stop valves are designed to fully close once tripped, any indication that the valve is no longer fully open is sufficient to determine trip status. Reactor trip on turbine trip is an anticipatory trip and should be developed as soon as there is clear indication that the turbine is tripping. Because the stop valves close so quickly, any indication near the fully open position (such as 90% open) provides sufficient assurance that the stop valve is going closed.
j i
d.
Provide a list of the Chapter 15 accidents analyses that relate to the Function 14.b j
and indicate the impact on these accidents from your proposed revision.
1 Reactor trip on turbine trip is an anticipatory trip and no credit is taken for it in i
e any of the Chapter 15 accident analyses. Therefore, the proposed TS change has no impact on the accidents described in FSAR Chapter 15. -
2.
You state that Notes 1 and 2 to Table 3.3.1-1, Overtemperature AT and Overpower AT, respectively, are proposed to be revised to refer to the " Nominal Trip Setpoint." In addition, these notes are proposed to be revised to delete the inequalities from the constants K1 through K6 (except for K5 2 0 for decreasing temperatures and K6 = 0 for T > T"), and T', T", and P'.
a.
You state that the uncertainty calculations assume that the as left tolerance (conservative and non-conservative direction) is satisfied on a reasonable, statistical basis, not the nominal condition is satisfied exactly. You further state that it is acceptable for the as left condition, immediately after calibration of process rack
U Y. Nuclear Regulatory Commission LCV-1102-B Page 5 modules for the bistable, to be in the non-conservative direction, as long as the magnitude is within the plant procedure specified calibration tolerance (which has been appropriately reflected in the protection of actuation function specified calibration tolerance). You conclude that therefore the trip setpoint inequalities provided in the above noted tables do not define absolute limits for the as left condition of the process rack modules. The limits are defined by the plant calibration procedures and reflected in the uncertainty calculations.
Ilow is the plant procedure specified calibration tolerance obtained and where is it documented? How do the nominal trip setpoint values compare to the calibration tolerance values?
The plant procedure calibration tolerance is defined in the Westinghouse Setpoint Uncertainty calculations. Westinghouse specifies the instrument loop (string) calibration tolerance which then defines the upper and lower calibration limits in the calibration procedure. For example, WCAP-ll269, Rev.1, specifies a total of five calibration tolerances for overtemperature AT in Table 3-
- 5. These calibration tolerances are:
0.5 % of span for the R/E, 0.5 % AT span for the AT process racks downstream of the R/E, 0.5 % AT span for the Tavg process racks, 0.5 % AT span for the Pressurizer Pressure racks and 0.5 % AT span for the AI racks.
Each module in the string (AT, Tavg, Pressurizer Pressure or A1) is calibrated to within i0.5 % of span of the desired value at each calibration point. Then all modules in a specific string in total are verified to be within 10.5 % of AT span.
This last check satisfies WCAP-11269, Rev.1. The voltages equivalent to the Nominal Trip Setpoint, the Upper Calibration Tolerance and the Lower Calibration Tolerance are specified for each calibration point in the plant calibration procedures. The Nominal Trip Setpoint value in the Technical Specifications is the same in the plant calibration procedure and conesponds to the mid-point between the Upper and Lower Calibration Tolerance values. An example is noted as Figure 1.
The gains (K,, K,, K,, K., K,, and K.) and reference values (T', T" and P') are now scaled over multiple process rack modules. This is to prevent the voltage saturation of the module by a plant transient. The gains are scaled exactly but in terms of voltage are distributed over multiple modules in the instrument string.
Thus, it is no longer possible to demonstrate that a gain or reference value is reflected in the calibration of the channel in a singular manner. The plant staff demonstrates an acceptable as left condition by determining that the overall calibration accuracy for the process module string is satisfied. The calibration I
U SINuclear Regulatory Commission LC% l102-B Page 6 accuracy is defined as noted above, in WCAP-11269, Rev.1, and reflected in engineering units and voltage in the calibration procedure. Thus "as close as reasonably possible" is defined as a reasonable attempt to approach zero volts as j
the deviation from desired for the calibration point of the instrument string of modules under test. This would be achieved by minimizing the calibration error for each module in the string. flowever, it is recognized that the achievement of a desired deviation of zero volts may not be possible thus, the upper and lower calibration tolerances define the maximum as left voltage deviation for the instrument string of modules under test.
Table 1 provides a list of the events in the Safety Analyses that utilize OTAT or OPAT as primary or backup trip functions.
Figure 1 Calibration Procedure Upper Calibration Tolerance n
l
+0.5% AT span Nominal Trip Setpoint (in WCAP.
11269, Rev.1, Technical Specifications, j
& Calibration Procedure)
\\
j s
t l
1 l
-0.5% ATspan i
Calibration Procedure Lower 2
Calibration Tolerance h
y l
l f
i
D a
r y
o r
r p
f pa ed i
m n n u
s r
t n a i
k i
e r a s c
T h p mn a
A t
o B
xxxx x
xx e
P t h ei t T
O nt ]
v a e r.
=
p i l A
v oi a
u t
P g
ef r c s t
vl e
O e
e a r a s p
e c i
[
h r u
s y
t e
t f
t k n gl a
or c on n o
n i
e i
c a cl a ir v
s b
a T
e e e n c y s c a os t e
yng n efe yr h
lat n ah a a
t a
f n pi t s t
n m
o a et a e i
e h
s e c i
ir c g s vt P
x e
h t
s t
a o lut n
T ly f et s ni a
oh r e ad t
o rl e A
n e
pm i
P a
r t
r s
o a p e e O
e h
sh u
h mt d yt s s
r ye t
l f
ol h a na i
p o
pc n
t e ma adi i
e e m r
e ni T
o o
r yi r
i t
t f r o s e sL p
m ].
on e f i r
at s k
f u
r ai k
o a s u s s s t
e u
a e
y et c
el a
nb b or h r a e r d e t
B xxxx xx x
an n
p e
o m
s sA oim gn T
r 1
o a ih E
A f e cTte n oy t
ait t
L T
ns n[ r h af t
e u
B O
ioe f. e cl a uS g
dh r
A tc r e ng oc a
i e
T nl h oh s lah p
t u
p e ct ir f a i s r s
t T
et d e o ytye o
e l
l r
r y
t n
rl i a n o h
i a
f cif n a l
r s t at e ywy t
u a
i b r b ye m
d l
t n a t
c r e,
e r
r s i om f n o i
c i
P x
xxxx ck i
l t l a ut a
pc e s
a lye xn u e
T i b e uf eh e r
t A
f h t v
c t
e t fi T
m oe r f or i
r l
O pa nh o o
t s a x e o,m yel n
et l
n ui n
o s
dd.
a a w l
e sl s
t el ed e.
i o
t v
a s a i
s ei c
p ss n
z n
ym ye e yi r
r nd f ct i
l o
r e
i o
a s lafi a e e
f m
u w
it i
e nd nif a r t
s m
c uh o
ar a
n a
s t
s k
u e e a
ei oc t
P n z u ya yr t o
d r r et or p e e t
oa nc s it t
C e
p u r r al a e Rw u
ef s s
i el t
u f t y
o Da eBl a u sR s
l a a f e e e n r
s i
t u
a r wie d
s e r
el a
a i
r oo e
r F F
a did o
w p w a D pb a
u wy d
r e s e sh t
e t
di a r e
o ga m
e n
e a c t t r
r t
lu a el a n o eP r d ne u r
t d e gb o t
a r a e v ni r t
di dh oDT c e r aF n pL e
g e
F mh t
cd e
al p ir i t e
pw moicP a t
r d n d e h a i
eiWoS o ni l
c n R
md a e l
sW BCt n e e c
o t
n a
if ch ei r
eeteS mr pmy AdRa aB e
i d
r po xt t
eh a TFSt e e t ir Sk pe nClet e i
e -
r t
te r
o s
r t
i s x r o r n n r
2 t
r n
lc0 n
e e e sf osb e yE T N e aCl oe e Ts Ti pai B R r t u1 e
aii rSf ef a t
r t
v vt G
yd t
t n
l N1 7 s
ws s v m i sdCgcd a me oga s s e on owAe n e r e pn o r n c i
ec cd a sb l
ov m at uii c
k ot pot n
p d ee SVe s r s e c pc el n g
a i
.Ca r
r ex x a e ou oeCn na e at n h s a i l nt i
nt r e e u ULP TT FEEI SLTLFRSUI S P s Bsf tap l
a U. S. Nuclear Regulatory Commission
]
' LCV-I l02-B Page 8 -
- b. You stat, %t for the purposes of channel calibration that the values specified in l
Notes 1 and 2 to Table 3.3.1-1 for K1, K2, K3, K4, K5 K6, T', T", and P' are utilized in the safety analyses without explicit tolerances, but should be considered as nominal values for instrument settings. That is, while an exact setting is not expected, a setting as close as reasonably possible is desired. Explain how "as close as
]
reasonably possible is desired" would be obtained.
I Please indicate the Chapter 15 accident analyses that are affected by the Overtemperature AT and Overpower AT trips. Do your proposed change impact these analyses to change the results in a non conservative way, Please refer to the enclosed copy of GP-16696 for a discussion of how "as close e
as reasonably possible" is obtained, and see the response to Question 2, above for -
I a tabulation of the Chapter 15 accident analyses.
3.
Please provide a copy of the reference 9, Westinghouse Letter GP-16646, November 5, 1997.
The correct letter number is GP-16696. As discussed above, a copy of this document is included with this submittal.
In a later discussion, the NRC staff requested information regarding the components of
" calibration tolerance" and the basis. The components and basis of the current Vogtle l
Instrumentation and Control programs are in accordance with WCAP-11269, Section 3.2, Items 7a and 7d (pgs 3-4 & 3-5). These items currently comprise the calibration tolerance and are described as follows:
item 7a, Rack Allowable Deviation, Rack Calibration Accuracy; e
i item 7d, Rack Allowable Deviation, Comparator Setting Accuracy.
e l
l la accordance with the requirements of 10 CFR 50.92, LCV-1102 included a Significant
(
Hazards Evaluation for the proposed changes. That evaluation is not affected by the changes l
proposed by this submittal.
l Sincerely, C. K. McCoy CKM/NJS i
i-U. S. Nuclear Regulatory Commission LCV-1102-B Page 9 -
Enclosure xc:
Southern Nuclear Operatina Comoany Mr. J. B. Beasley, Jr.
Mr. M. Sheibani NORMS U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. D. H. Jaffe, Senior Project Manager, NRR Mr. John Zeiler, Senior Resident Inspector, Vogtle i
INSERT FOR BASES PAGE B 3.3-109 Amendments 38 (Unit 1) and 18 (Unit 2), ESFAS Safety Injection Pressurizer - Low allowable value revision.
I l
Amendments 34 (Unit 1) and 14 (Unit 2), RTS Steam Generator Water Level -Low Low, l
ESFAS Turbine Trip and Feedwater Isolation SG Water Level - High High, and ESFAS AFW SG water Level - Low Low.
l l
Amendments 43 and 44 (Unit 1) and 23 and 24 (Unit 2), revised ESFAS Interlocks Pressurizer P-11 trip setpoint and allowable value.
i i
l l
l l
RTS instrumentation 3.3.1 Table 3.3.1 1 (page 1 of 8)
Reactor Trip System Instrtsnentation l
APPLICABLE MODES OR OTHER NOMINAL l
SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP I FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETP0lNT "I l
1.
Manual Reactor 1,2 2
8 SR 3.3.1.13 NA NA Trip 3(a), 4(a), 5(a) 2 C
SR 3.3.1.13 NA NA 2.
Power Range Neutron Flux a.
High 1,2 4
0 SR 3.3.1.1 5 111.3% RTP 109% RTP l
SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 b.
Low 1(b) 2 4
E SR 3.3.1.1 5 27.3% RTP 25% RTP l
SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15 3.
Power Range 1,2 4
E SR 3.3.1.7 5 6.3% RTP 5% RTP l
Neutron Flux High SR 3.3.1.11 with time with time Positive Rate constant constant t 2 see a 2 sec 4.
Intermediate Range 1(b), 2(C) 2 F,G SR 3.3.1.1 5 31.1% RTP 25% RTP l
Neutron Flux SR 3.3.1.8 SR 3.3.1.11 2(d) 2 H
SR 3.3.1.1 5 31.1% RTP 25% RTP l
SR 3.3.1.8 SR 3.3.1.11 (continued)
(a) With Reactor Trip Breakers (Rf8s) closed and Rod Control System capable of rod withdrawal.
(b) Below the P 10 (Power Range Neutron Flux) interlocks.
(c) Above the P-6 (Intermediate Range Neutron Flux) Interlocks.
(d) Below the P 6 (Intermediate Range Neutron Flux) interlocks.
(n) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
1 i
Vogtle Units 1 and 2 3.3-14 Amendment No.
(Unit 1) l Amendment No.
(Unit 2)
\\
l L
RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 2 of 8)
Reactor Trip System instrumentation l
l APPLICABLE N00ES OR OTHER NOMINAL l'
SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CON 0lil0NS CHANNELS CON 0lil0NS REQUlkEMENTS VALUE SETPolNT(n) g j
5.
Source Range 2(d) 2 1,J SR 3.3.1.1 5 1.4 E9 1.0 E5 l
Neutron Flux SR 3.3.1.8 cps cps SR 3.3.1.11 SR 3.3.1.15 3(a), 4(a), $(a) 2 J,K SR 3.3.1.1 5 1.4 E5 1.0 ES l
SR 3.3.1.7 cps eps SR 3.3.1.11 SR 3.3.1.15 3('), 4(*), 5(')
1 L
SR 3.3.1.1 NA NA SR 3.3.1.11 6.
Overtenperature AT 1,2 4
E SR 3.3.1.1 Refer to Refer to SR 3.3.1.3 Note 1 Note 1 SR 3.3.1.6 (Page (Page i
SR 3.3.1.7 3.3 20) 3.3 20) i SR 3.3.1.10 i
l SR 3.3.1.15 7.
Overpower AT 1,2 4
E SR 3.3.1.1 Pefer to Refer to j
SR 3.3.1.7 Note 2 Note 2 SR 3.3.1.10 (Page (Page SR 3.3.1.15 3.3 21) 3.3 21) l (continued)
(a) - With RTes closed and Rod control System capable of rod withdrawal.
(d) Selow the P 6 (Intermediate Range Neutron Flux) interlocks.
(e) With the RT5s open. In this condition, source range Function does not provide reactor trip but does provide j
input to the High Flux et Shutdown Alarm System (LC0 3.3.8) and indication.
(n) A channel is OPERASLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
Vogtle Units 1 and 2 3.3-15 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
I RTS Instrumentation 3.3.1 Ta5le 3.3.1 1 (page 3 of 8)
Reactor Trip System Instrtmentation APPLICA8LE MODES OR OTHER NOMINAL l
SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CON 0!TIONS CHANNELS CON 0lil0NS REQUIREMENTS VALUE SETPolNT(n) g j
8.
Pressurizer Pressure a.
Low 1(I) 4 M
SR 3.3.1.1 a 1950 psig 1960(8) l l
SR 3.3.1.7 psig l
SR 3.3.1.10 l
SR 3.3.1.15 b.
High 1,2 4
E SR 3.3.1.1 s 2395 psig 2385 psis l
SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 9.
Pressurizer Water 1(I) 3 M
SR 3.3.1.1 5 93.9%
92%
l Level - High SR 3.3.1.7 SR 3.3.1.10
- 10. Reactor Coolant F low - Lcw a.
Single Loop 1(h) 3 per N
SR 3.3.1.1 e 89.4%
90%
l loop SR 3.3.1.7 t
SR 3.3.1.10 I
SR 3.3.1.15 i
b.
Two Loops 1(I) 3 per M
SR 3.3.1.1 t 89.4%
90%
j Loop SR 3.3.1.7 SR 3.3.1.10 1
I SR 3.3.1.15 l
(continued) j (f) Above the P 7 (Low Power Reactor Trips Block) Interlock.
l (g) Time constants utilfred in the lead lag controller for Pressurizer Pressure Low are 10 seconds for lead and 1 l
second for lag.
(h) Above the P 8 (Power Range Neutron Flux) interlock.
l (f) Above the P-7 (Low Power Reactor Trips Block) inter!ock and below the P 8 (Power Range Neutron Flux) interlock.
(n) A chahnel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the i
l Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip setpoint may be set enore conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
Vogtle Units 1 and 2 3.3-16 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
i l
l RTS instrumentation i
3.3.1 j
I l-1 Table 3.3.1 1 (page 4 of 8) l Reactor Trip System Instrunentation j
l APPLICA8LE MODES OR OTHER NOMINAL l
SPECIFIED REQUIRED SURVEILLANCE ALLOWA8LE TRIP I FUNCTION CON 0!TIONS CHANNELS CON 0lf!ONS REQUIREMENTS VALUE SETPOINT "3 l
l 11.
Undervoltage 1(I) 2 per M
SR 3.3.1.9 t 9481 V 9600 V l
l SR 3.3.1.15 j
12.
Underfrequency l(f) 2 per M
SR 3.3.1.9 a $7.1 Hz 57.3 Hz l
RCPs bus SR 3.3.1.10 SR 3.3.1.15 l
l 13.
Steam 1,2 4 per SG E
SR 3.3.1.1 2 35.9%
37.8%
l Generator (SG)
SR 3.3.1.7 Water Level - Low SR 3.3.1.10 4
Low SR 3.3.1.15 j
i I
(continued)
(f) Above the P 7 (Low Power Reactor Trips Block) interlock.
}
I (n) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the i
Trip Setpoint value is conservative with respect to its associated Attowable value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
i i
l I
i I
i i
Vogtle Units 1 and 2 3.3-17 Amendment No.
(Unit 1)
Amendment No.
(Unit 2) l l
i
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 8)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER NONINAL l
SPECIFIED REQUIRED SURVEILLANCE ALLOWA8LE TRIP I FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT ")
l
- 14. Turbine Trip a.
Low Fluid oil 1(I) 3 0
SR 3.3.1.10 t 500 psig 580 psig l
Pressure SR 3.3.1.16 b.
Turbine stop 1(I) 4 P
SR 3.3.1.10 t 90%
96.7%
l Valve closure SR 3.3.1.14 open open
- 15. Safety 1,2 2 trains e
SR 3.3.1.13 NA NA Injection (SI)
Input from Engineered Safety Feature Actuation System (ESFAS)
- 16. Reactor Trip System Interlocks a.
Intermediate 2(d) 2 R
SR 3.3.1.11 2 6E 11 amp 1E 10 amp l
Range Neutron SR 3.3.1.12 Flux, P 6 b.
Low Power 1
1 per S
SR 3.3.1.5 NA NA Reactor Trips train Block, P 7 4
S SR 3.3.1.11 5 50.3% RTP 48% RTP l
c.
Power Range 9
Neutron Flux, SR 3.3.1.12 P-8 d.
Power Range 4
S SR 3.3.1.11 5 52.3% RTP 50% RTP l
Neutron Flux, 1
Power Range 4
R SR 3.3.1.11 (l,m)
(t,m)
Neutron Flux, 1,2 SR 3.3.1.12 l
P 10 and input to P-7 2
S SR 3.3.1.10 s 12.3%
10%
l f.
Turbine lapulse 1
SR 3.3.1.12 Impulse Inpulse Pressure, P 13 Pressure Pressure Equivalent Equivalent turbine turbine (continued) j (d) Below the P 6 (Intermediate Range Neutron Flux) interlocks.
j (j) Above the P-9 (Power Range Neutron Flux) Interlock.
l (t) For the P 10 input to P-7, the Allowable Value is s 12.3% RTP and the Nominal Trip Setpoint is 10% RTP.
l l
l (m) For the Power Range Neutron Flux, P-10, the Allowable Value is t 7.7% RTP and the Nominal Trip Setpoint is l
10% RTP.
(n) A channel is OPERA 8LE with cn actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
Vogtle Units 1 and 2 3.3-18 Amendment No.
(Unit 1)
Amendment No.
(Unit 2) 1
RTS Instrumentation l
3.3.1 Tabte 3.3.1-1 (page 6 of 8)
Reactor Trip System Instrumentation l
APPLICA8LE MODES I
OR OTHER NOMINAL l
l SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP j
FUNCTION CONDITIONS CHANNELS CONDITIONS LEQUIREMENTS VALUE SETPOINT(n) l
- 17. Reactorgp 1,2 2 trains T,V SR 3.3.1.4 NA NA areakers i
3(*), 4(*), 5(*)
2 trains C
SR 3.3.1.4 NA NA
- 18. Reactor Trip 1,2 1 each U,V SR 3.3.1.4 NA NA l
Breaker per RTB Undervoltage and Shunt Trip 3(*), 4(a), 5(*)
1 each C
SR 3.3.1.4 NA NA I
Mechanisms per RTS
- 19. Automatic Trip 1,2 2 trains 0,V SR 3.3.1.5 NA NA i
Logic 3(*), 4(*), 5(*)
2 trains C
SR 3.3.1.5 NA NA (a) With RTBs closed and Rod Control System capable of rod withdrawal.
(k) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.
l (n) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-l adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
I i
l l
l l
i Vogtle Units 1 and 2 3.3-19 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
(
RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 7 of 8) i Reactor Trip System Instrunentation Note in Overtencerature Delta-T The overtemperature Delta-T Function Allowable Value shall not exceed the Nominal Trip Setpoint defined by the j
following equation by more than 2.25% of RTP.
100 g (1 + f,s) 1 (1 +f s) 1 T
- T'
- K (P' - P) - f, ( AFD)
K, - K {1 + f.s)
(1 + f,s) 5 8
3 N, (1 + f,s) (1 + f s) 3 Where:
AT measured loop specific RCS dif ferentist tenperature, degrees F l
AT.
Indicated loop specific RCS differential at RTP, degrees F i
ItLa lead lag compensator on measured dif ferential tenperature l
1+fas f, fa time constants utilized in lead lag compensator for differential temperatures f, t 8 seconds, i
f, s 3 seconds 1
1+f s lag conpensator on measured dif ferential tenperature 3
(
f time constant utilized in lag conpensator for dif ferentist tenperature, s 2 seconds 3
K, fundamental setpoint, 5112% RTP K,
modifier for temperature, = 2.24% RTP per degree F ltL1 1+f.s lead-lag conpensator on dynamic tenperature conpensation f.,
f.
time constants utilized in lead-lag compensator for tenperature conpensation:
- f. t 28 seconds, f s 4 seconds T
measured loop specific RCS average temperature, degrees F 1
1+f.s lag conpensator on measured everage tenperature l
f.
time constant utilized in las conpensator for average temperature, = 0 seconds T'
indicated loop spec 1fic RCS average temperature at RTP, s 588.4 degrees F K
modifier for pressure, = 0.115% RTP per psig 3
t P
measured RCS pressurizer pressure, psig P'
reference pressure, t 2235 psig a
Laplace transform variable, inverse seconds f,( AFD) omdifier for Axial Flux Difference (AFD):
1.
for AFD between 32% and +10%, = 0% RTP 2.
for each % AFD is below 32%, the trip setpoint shall be reduced by 3.25% RTP 3.
for each % AFD is above +10%, the trip setpoint shall be reduced by 2.7% RTP Vogtle Units 1 and 2 3.3-20 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
l RTS Instrumentation l
3.3.1 i
l Table 3.3.1 1 (page 8 of 8)
Reactor Trip System Instrunentation l
Note 2: Overoower Delta T The overpower Delta T Function ALLOWABLE VALUE shall not exceed the Nominal Trip Setpoint defined by the following l
equation by more than 2.85% of RTP.
100 y (1 +f,s) 1 (f,s) 1 1
5 K, -
-T"
- f,( AFD)
N, (1 + f,s) L1 + f s)
K, (1 + f,s) (1 + f,s) T - K, T (1 + f.)
3 Where:
AT measured loop specific RCS differential temperature, degrees F AT, indicated loop specific RCS differential at RTP, degrees F j+Lg lead-lag compensator on measured dif ferential tenperature 1 +f,s f, f, time constants utilized in lead lag compensator for dif ferential temperatures fi t 8 seconds, i
f s 3 seconds 1
1+f s lag compensator on measured dif ferential tenperature 3
time constant utilized in las conpensator for differential temperature, s 2 seconds 53 K,
fundamental setpoint, 5109.5% RTP K
modiffer for temperature changes t 2% RTP per degree F for increasing terrperature, t 0% RTP 6
per degree F for decreasing tenperature
.liL 1+f,s rate tag compensator on dynamic tenperature cospensation f,
time constant utilized in rate lag cospensator for tenperature compensation, t 10 seconds T
measured loop spectfic RCS average tenperature, degrees F 1
1+f s lag compensator on measured everage teoperature f,
time constant utilized in las conpensator for everage temperature, = 0 seconds l
K, modifier for temperature: 2 0.20% RTP per degree F for T > T", = 0% RTP for T $ T" T*
Indicated loop specific RCS average temperature at RTP, 5 588.4 degrees F s
Laplace transform variable, inverse seconds f,( AFD )
modifier for Axial Flux Difference (AFD), = 0% RTP for all AFD Vogtle Units 1 and 2 3.3-21 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
a ESFAS Instrumentation 3.3.2 l
l i
Table 3.3.2 1 (page 1 of 7)
Engineered Safety Feature Actuation System Instrumentation 1
l APPLICABLE l
NODES OR l
OTHER NOMINAL l
SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP l
FUNCTION CON 0lfl0NS CHANNELS CONDITIONS REQUIRENENTS VALUE SETPolNTIII l
1.
Safety injection I
a.
Manual Initiation 1,2,3,4 2
B SR 3.3.2.6 NA NA b.
Automatic 1,2,3,4 2
C SR 3.3.2.2 NA NA l
Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays l
c.
Contalrunent 1,2,3 3
0 SR 3.3.2.1 s 4.4 pels 3.8 psig l
Pressure - High 1 SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.8 d.
Pressurizer 1,2,3(a) 4 0
sa 3.3.2.1 2 1856 psig 1870 psig l
Pressure - Low SR 3.3.2.4 l
SR 3.3.2.7 SR 3.3.2.8 e.
Steam Line 1,2,3(a) 3 per D
SR 3.3.2.1 2 570(b) 585(b) l Pressure Low steam SR 3.3.2.4 pois pels line SR 3.3.2.7 SR 3.3.2.8 (continued)
(a) Above the P-11 (Pressurizer Pressure) Interlock.
(b) Time constants used in the lead /las controller are t, t 50 seconds and ta s 5 seconds.
(i) A channel is OPERABLE witn an actual Trip Setpoint value outside its calibration tolerance band provided the Trip setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominat. Trip Setpoint. A Trip setpoint may be set more conservative than the Nominal Trip setpoint as necessary in response to plant conditions.
I L
Vogtle Units 1 and 2 3.3-30 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
1 1
ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 2 of 7)
Engineered Safety Feature Actuation System Instrunentation APPLICA8LE MODES OR OTHER NOMINAL l
SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP III l
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPolNT 2.
Contairunant spray a.
Ma u l Initiation 1,2,3,4 2
8 SR 3.3.2.6 NA NA b.
Automatic 1,2,3,4 2
C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays c.
Containment Pressure H igh - 3 1,2,3 4
E SR 3.3.2.1 5 22.4 psig 21.5 psig l
SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.8 (continued)
(f) A chsmel is OPERA 8tE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip setcoint value is conservative with respect to its associated Allowable Value and the chamel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Sstpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
I Vogtle Units 1 and 2 3.3-31 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
i ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 3 of 7)
Engineered Safety Feature Actuation System Instrumentation APPLICA8LE MODES OR OTHER NOMINAL l
SPECIFIED REQUIRED SURVE!LLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CON 0lTIONS REQUIREMENTS VALUE SETPOINT(II l
r l
3.
Phase A Contalrumant isolation I
(a) Manual Initiation 1,2,3,6 2
s SR 3.3.2.6 NA NA (b) Automatic 1,2,3,4 2 trains C
SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (c) Safety Injection Refer to Function 1 (Safety injection) for all initiation funetions and requirements.
4 Steam Line Isolation s.
Nanual Initiation 1,2(c) 3(c) 2 F
SR 3.3.2.6 NA NA b.
Automatic 1,2(c) 3(c) 2 G
SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (continued)
(c) Except when one main steam isolation valve and associated bypass isolation valve per steam line is closed.
(i) A channel is OPERA 8LE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
Vogtle Units 1 and 2 3.3-32 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 4 of 7)
Engineered Safety Feature Actuation System Instrumentation APPLICA8LE MCCES OR OTHER NOMINAL
\\
SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP II) l FUNCTION CON 0lTIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPolNT 4.
Steam Line Isolation (continued) c.
Containment 1,2(C) 3 0
SR 3.3.2.1 s 15.4 psig 14.5 psig l
Pressure - High 2 3(e)
SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.8 d.
Steam Line Pressure (1) Low 1,2(c) 3 per 0
SR 3.3.2.1 a 570 (D) 585 (D) l steam SR 3.3.2.4 psig psig 3(a)(c) line SR 3.3.2.7 SR 3.3.2.8 (2) Negative 3(d)(c) 3 per 0
SR 3.3.2.1 5 125 (*)
100 (')
l Rate - H igh steam SR 3.3.2.4 psi /sec psi /see line SR 3.3.2.7 SR 3.3.2.8 (continued)
(a) Above the P 11 (Pressurizer Pressure) interlock.
(b) Time constants used in the lead / lag controller are t, a 50 seconds and t, 5 5 seconds.
(c) Except when one main steam isolation valve and associated bypass isolation valve per steam line is closed.
(d) Below the P 11 (Pressurizer Pressure) interlock.
(e) Time constant utilized in the rate / leg controller is a 50 seconds.
(1) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibrati e tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
Vogtle Units 1 and 2 3.3-33 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 5 of 7) l Engineered Safety Feature Actuation System Instrunentation 1
APPLICABLE MODES OR OTWER NOMINAL l
l SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT(I) l l
i 5.
Turbine Trip and Feedwater Isolation l
a.
Automatic 1,2(f) 2 trains H
SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Reisys b.
Low RCS Teve 1,2(I) 4 I
SR 3.3.2.1 t 561.5 'F 564 'F l
SR 3.3.2.4 SR 3.3.2.7 Coincident with Refer to Function 8a for all P 4 requirements.
SR 3.3.2.1 5 87.9%
86.0%
l Level - High High SR 3.3.2.4 (P 14)
SR 3.3.2.7 SR 3.3.2.8 d.
Safety injection Refer to Function 1 (Safety injection) for all initiation functions and requirements.
6.
Automatic 1,2,3 2 trains G
SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays b.
SR 3.3.2.1 a 35.9%
37.8%
l Level - Low Low SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.8 (continued)
(f) Except when one MFly or MFRV, and its associated bypass valve per feedwater line is closed and deactivated or isolated by a closed manual valve.
(i) A channel is OPERA 8LE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip Setpoint u necessary in response to plant conditions.
Vogtle Units 1 and 2 3.3-34 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
I ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of ')
Engineered Safety Feature Actuation Systek umentation i
i APPLICA8LE l
MODES OR l
OTHER NOMINAL l
l SPECIFIED REQUIRED SURVEILLANCd ALLOWABLE TRIP III l
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPolNT l
6.
Auxiliary Feedwater (continued) c.
Safety Injection Refer to Function 1 (Safety injection) for all initiation functions and requirements.
d.
Trip of all Main 1,2(8) 1 per J
SR 3.3.2.6 NA NA Feedwater Ptsps pop 7.
Semi-automatic Switchover to containment Sump a.
Automatic 1,2,3,4(h) 2 c
SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Retsys b.
Refueling Water 1,2,3,4 4
K SR 3.3.2.1 2 264.9 in.
275.3 In.
l Storage Tank SR 3.3.2.4 (RWST) Level - Low SR 3.3.2.7 Low SR 3.3.2.8 Coincident with Refer to Function 1 (Safety injection) for all initiation Safety injection ftnctions and requirements.
(continued)
(g) When the Main Feedwater System is operating to supply the SGs.
(h) In MODE 4, only 1 train is required to be OPERABLE to support semi automatic switchover for the RHR pw p that is required to be OPERA 8LE in accordance with Specification 3.5.3, ECCS shutdown.
(i) A channel is OPERABLE with an actual Trip Setpoint value outside its calibration tolerance band provided the Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip setpoint may be set more conservative than the Nominal Trip Setpoint as necessary in response to plant conditions.
I i
l i
Vogtle Units 1 and 2 3.3-35 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
ESFAS Instrumentation 3.3.2 Table 3.3.2 1 (page 7 of 7)
Engineered Safety Feature Actuation System Instrunentation APPLICA8LE N00ES OR
(
OTHER NOMINAL l
SPECIFIED REQUIRED SURVE!LLANCE ALLOWABLE TRIP EI)
FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT l
- 8. ESFAS Interlocks
- a. Reactor Trip, P 4 1,2,3 1 per F
SR 3.3.2.9 NA NA train, 2 trains I
l
- b. Pressurizer Pressure, 1,2,3 3
L SR 3.3.2.4 s 2010 psig 2000 psig l
l P-11 SR 3.3.2.7 i
l (1) A channel is OPERA 8LE with an actual Trip Setpoint value outside its calibration tolerance band provided the l
Trip Setpoint value is conservative with respect to its associated Allowable Value and the channel is re-l adjusted to within the established calibration tolerance band of the Nominal Trip Setpoint. A Trip Setpoint may be set more conservative than the Nominal Trip setpoint as necessary in response to plant conditions.
i I
l l
l l
l l
\\
t l
l Vogtle Units 1 and 2 3.3-36 Amendment No.
(Unit 1)
Amendment No.
(Unit 2) t
RTS Instrumentation B 3.3.1 BASES BACKGROUND Sianal Process Control and Protection System (continued) the other channels providing the protection function actuation. Again, a single failure will neither cause nor prevent the protectior. fur.ction actuation.
These requirements are described in IEEE-279-1971 (Ref. 4).
The actual number of channels required for each unit parameter is specified in Reference 1.
Two logic channels are required to ensure no single random failure of a logic channel will disable the RTS.
The logic channels are designed such that testing required while the reactor is at power may be accomplished without causing trip.
Provisions to allow removing logic channels from service during maintenance are unnecessary because of the logic system's designed reliability.
Trio Setooints and Allowable Values The Trip Setpoints are the nominal values at which the bistables are set. Any bistable is considered to be properly adjusted when the "as left" value is within the band for CHANNEL CALIBRATION tolerance.
l The Trip Setpoints used in the bistables are based on the analytical limits stated in Reference 1.
The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. To allow for calibration tolerances, instrumentation uncertainties, instrument drift, and severe environment errors for those RTS channels that must function in harsh environments as defined by 10 CFR 50.49 (Ref. 5),
the Trip Setpoints and Allowable Values specified in Table 3.3.1-1 in the accompanying LC0 are conservatively adjusted with respect to the analytical limits. A detailed description of the methodology used to calculate the Trip Setpoints, including their explicit uncertainties, is provided in the "RTS/ESFAS Setpoint Methodology Study" (Ref. 6). The actual nominal Trip Setpoint entered into the bistable is more conservative than that specified by the Allowable Value to account for changes in random measurement errors detectable by a COT. One example of such a change in measurement error is drift during the surveillance interval.
(continued)
Vogtle Units 1 and 2 8 3.3-4 Revision No.
RTS instrumentation B 3.3.1 BASES BACKGROUND Trio Setooints and Allowable Values (continued)
If the measured setpoint does not exceed the Allowable l
Value, the bistable is considered OPERABLE.
[
Setpoints in accordance with the Allowable Value ensure that SLs are not violated during A00s (and that the consequences j
l of DBAs will be acceptable, providing the unit is operated l
from within the LCOs at the onset of the A00 or DBA and the l
equipment functions as designed).
For the purpose of demonstrating compliance with 10 CFR 50.36 to the extent I
that the Technical Specifications are required to specify Limiting Safety System Settings (LSSS), the LSSS for VEGP J
are comprised of both the Nominal Trip Setpoints and the Allowable Values specified in Table 3.3.1-1.
The Nominal i
Trip Setpoint'is~the expected value to be achieved during calibrations. The Nominal Trip Setpoint considers all factors which may affect channel performance by statistically combining rack drift, rack measurement and test equipment effects, rack calibration accuracy, rack comparator setting accuracy, rack temperature effects, sensor measurement and test equipment effects, sensor calibration accuracy, primary element accuracy, and process measurement accuracy. The Nominal Trip Setpoint is the value that will always ensure that safety analysis limits are met (with margin) given all of the above effects.
The Allowable Value has been established by considering the values assumed for rack effects only.
The Allowable Value serves as an operability limit for the purpose of the quarterly CHANNEL OPERATIONAL TESTS.
Each channel of the process control equipment can be tested 1
on line to verify that the signal or setpoint accuracy is within the specified allowance requirements of Reference 2.
Once a designated channel is taken out of service for testing, a simulated signal is injected in place of the field instrument signal. The process equipment for the channel in test is then tested, verified, and calibrated.
SRs for the channels are specified in the SRs section.
The Trip Setpoints and Allowable Values listed in Table 3.3.1-1 are based on the methodology described in Reference 6, which incorporates all of the known uncertainties applicable for each channel. The magnitudes of these uncertainties are factored into the determination of each Trip Setpoint. All field sensors and signal (continued) i Vogtle Units 1 and 2 B 3.3-5 Revision No.
RTS Instrumentation B 3.3.1 BASES l
BACKGROUND Trio Setooints and Allowable Values (continued) processing equipment for these channels are assumed to operate within the allowances of these uncertainty magnitudes.
Solid State Protection System The SSPS equipment is used for the decision logic processing of outputs from the signal processing equipment bistables, i
To meet the redundancy requirements, two trains of SSPS, each performing the same functions, are provided.
If one train is taken out of service for maintenance or test' purposes, the second train will provide reactor trip and/or i
ESF actuation for the unit.
If both trains are taken out of service or placed in test, a reactor trip will result.
Each train is packaged in its own cabinet for physical and i
electrical separation to satisfy separation and independence l
l I
l i
i I
l (continued)
Vogtle Units 1 and 2 8 3.3-Sa Revision No.
RTS Instrumentation B 3.3.1 BASES i
THIS PAGE INTENTIONALLY LEFT BLANK (continued)
Vogtle Units 1 and 2 B 3.3-5b Revision No.
i
r RTS Instrumentation B 3.3.1 BASES l
BACKGROUND Reactor Trio Switchaear (continued) trip mechanism is sufficient by itself, thus providing a diverse trip mechanism.
1 The decision logic matrix Functions are described in the functional diagrams included in Reference 1.
In addition to the reactor trip or ESF, these diagrams also describe the various " permissive interlocks" that are associated with unit conditions.
Each train has a built in testing device that can automatically test the decision logic matrix Functions and the actuation devices while the unit is at power. When any one train is taken out of service for testing, the other train is capable of providing unit monitoring and protection until the testing has been completed. The testing device is semiautomatic to minimize testing time.
APPLICABLE The RTS functions to maintain the SLs during all A00s and SAFETY ANALYSES, mitigates the consequences of DBAs in all MODES in LC0, and LCO, and which the RTBs are closed.
APPLICABILITY Each of the analyzed accidents and transients can be detected by one or more RTS Functions. The accident analysis described in Reference 3 takes credit for most RTS trip Functions.
RTS trip Functions not specifically credited in the accident analysis are qualitatively credited in the safety analysis and the NRC staff approved licensing basis for the unit.
These RTS trip functions may provide protection for conditions that do not require dynamic transient analysis to demonstrate Function performance.
They may also serve as backups to RTS trip Functions that were credited in the accident analysis.
The LC0 requires all instrumentation performing an RTS Function, listed in Table 3.3.1-1 in the accompanying LCO, to be OPERABLE.
Failure of any instrument renders the affected channel (s) inoperable and reduces the reliability of the affected Functions. The Nominal Trip Setpoint column is modified by a Note that requires the as-left condition for a channel to be within the calibration tolerance for that channel.
In addition, the as-left condition may be more conservative than the specified Nominal Trip Setpoint.
I l
(continued)
Vogtle Units 1 and 2 B 3.3-7 Revision No.
RTS Instrumentation B 3.3.1 BASES APPLICABLE The conservative direction is established by the direction SAFETY ANALYSES, of the inequality applied to the Allowable Value.
It is I
LCO, AND consistent with the setpoint methodology for the as-left APPLICABILITY trip setpoint to be outside the calibration tolerance but in (continued) the conservative direction with respect to the Nominal Trip j
Setpoint.
For example, the Power Range Neutron Flux High trip setpoint may be set to a value less than 109% during initial startup following a refueling outage until a sufficiently high reactor power is achieved so that the power range channels may be calibrated.
In addition, certain Required Actions may require that the Power Range Neutron Flux High trip setpoints and/or the Overpower Delta-T setpoints be reduced based on plant conditions.
The LC0 generally requires OPERABILITY of four or three channels in each instrumentation Function, two channels of Manual Reactor Trip in each logic Function, and two trains in each Automatic Trip Logic Function.
Four OPERABLE i
(continued)
Vogtle Units 1 and 2 B 3.3-7a Revision No.
{
RTS Instrumentation l
l B 3.3.1 l
BASES l
THIS PAGE INTENTIONALLY LEFT BLANK (continued) 1 Vogtle Units 1 and 2 B 3.3-7b Revision No.
i RTS Instrumentation B 3.3.1 BASES APPLICABLE 6.
Overtemoerature AT (continued)
SAFETY ANALYSES, LCO, and This results in a two-out-of-four trip logic.
Section APPLICABILITY 7.2.2.3 of Reference 1 discusses control and protection system interactions for this function. Note that this Function also provides a signal to generate a turbine runback prior to reaching the Trip Setpoint.
A turbine runback will reduce turbine power and reactor power. A reduction in power will normally alleviate the Overtemperature AT condition and may prevent a reactor trip.
Delta-T, as used in the overtemperature and cverpower o
AT trips, represents the 100% RTP value as measured for each loop. This normalizes each loop's AT trips to the actual operating conditions existing at the time of measurement, thus forcing the trip to reflect the equivalent full power conditions as assumed in the accident analyses. These differences in RCS loop AT can be due to several factors, e.g., differences in RCS loop flows and slightly asymmetric power distributions between quadrants. While RCS loop flows are not expected to change with cycle life, radial power redistribution between quadrants may occur, resulting in small changes in loop specific AT values.
Therefore, loop specific AT values are measured as o
needed to ensure they represent actual core conditions.
The parameter K is the principal setpoint gain, since k
it defines the. unction offset. The parameters K and K define the temperature gain and pressure gain,2 3
l respectively. The values for T' and P'are key l
reference parameters corresponding directly to plant l
safety analyses initial conditions assumptions for the Overtemperature AT function.
For the purposes of performing a CHANNEL CALIBRATION, the values for K,
i K
K,
T', and P' are utilized in the safety analyses wi,tho'utexplicittolerances,butshouldbeconsidered l
as nominal values for instrument settings.
That is, while an exact setting is not expected, a setting as close as reasonably possible is desired.
Note that for T', the value for the hottest RCS loop will be set i
(continued)
Vogtle Units 1 and 2 B 3.3-16 Revision No.
RTS Instrumentation B 3.3.1 BASES APPLICABLE 6.
'Overtemoerature AT (continued)
SAFETY. ANALYSES,
'LCO, and as close as possible to 588.4*F. The value of T' for APPLICABILITY the remaining RCS loops will be set appropriately less than 588.4*F-based on the actual loop specific indicated T The engineering scaling calculations useeachof,Yhereferencedparametersasanexactgain or reference value.
Tolerances are not applied to the individual gain or reference parameters.
Tolerances are applied to each calibration module and the overall string calibration. In order to ensure that the Overtemperature AT setpoint is consistent with the assumptions of the safety analyses, it is necessary to verify during the CHANNEL OPERATIONAL TEST that the Overtemperature AT setpoint is within the appropriate calibration tolerances for the defined calibration conditions (Ref. 9).
The LC0 requires all four channels of the Overtemperature AT trip Function to be OPERABLE. Note that the Overtemperature AT Function receives input from channels shared with other RTS Functions.
Failures that affect multiple Functions require entry into the Conditions applicable to all affected Functions.
In MODE 1 or 2, the Overtemperature AT trip must be OPERABLE to prevent DNB.
In MODE 3, 4, 5, or 6, this trip Function does not have to be OPERABLE because the reactor is not operating and there is insufficient heat production to be concerned about DNB.
(continued)
)
Vogtle Units 1 and 2 8 3.3-16a Revision No.
RTS Instrumentation B 3.3.1 BASES THIS PAGE INTENTIONALLY LEFT BLANK.
i (continued)
Vogtle Units 1 and 2 B 3.3-16b Revision No.
I RTS Instrumentation B 3.3.1 BASES APPLICABLE 7.
Overoower AT (continued)
SAFETY ANALYSES, LCO, and Delta-T, as used in the overtemperature and overpower o
APPLICABILITY AT trips, represents the 100% RTP value as measured for each loop. This normalizes each loop's AT trips to the actual operating conditions existing at the time of measurement, thus forcing the trip to reflect the equivalent full power conditions as assumed in the accident analyses. These differences in RCS loop AT can be due to several factors, e.g., difference in RCS loop flows and slightly asymmetric power distributions between quadrants. While RCS loop flows are not expected to change with cycle life, radial power redistribution between quadrants may occur, resulting in small changes in loop specific AT values.
Therefore, loop specific AT values are measured as i
o needed to ensure they represent actual core conditions.
The value for T" is a key reference parameter corresponding directly to plant safety analyses initial conditions assumptlons for the Overpower AT function.
For the purposes of performing a CHANNEL
' K, and T" are CAllBRATION, the values for K, K'itho'ut explicit 4
utilized in the safety analyses w tolerances, but should be considered as nominal values for instrument settings. That is, while an exact setting is not expected, a setting as close as reasonably possible is desired. Note that for T",
the value for the hottest RCS loop will be set as close as possible to 588.4 F.
The value of T" for the remaining RCS loops will be set appropriately less than 588.4'F based on the actual loop specific indicated T The engineering scaling calculations useeachof,Thereferencedparametersasanexactgain or reference value. Tolerances are not applied to the individual gain or reference parameters.
Tolerances are applied to each calibration module and the overall string calibration.
In order to ensure that the Overpower AT setpoint is consistent with the assumptions of the safety analyses, it is necessary to verify during the CHANNEL OPERATIONAL TEST that the Overpower AT setpoint is within the appropriate calibration tolerances for defined calibration conditions (Ref. 9).
Note that for the parameter K,
3 (continued)
Vogtle Units 1 and 2 8 3.3-18 Revision No.
RTS Instrumentation B 3.3.1 BASES APPLICABLE 7.
Overoower AT -(continued)
SAFETY ANALYSES, LCO, and in the case of decreasing temperature, the gain APPLICABILITY setting must be 2: 0 to prevent generating setpoint margin on decreasing temperature rates.
Similarly, the setting for K is required to be equal to O for conditionswhereksT".
The LCO requires four channels of the Overpower AT trip Function to be OPERABLE. Note that the Overpower AT trip Function receives input from channels shared with other RTS Functions.
Failures that affect multiple Functions require entry into the Conditions applicable to all affected Functions.
In MODE 1 or 2, the Overpower AT trip Function must be OPERABLE. These are the only times that enough heat is generated in the fuel to be concerned about the heat generation rates and overheating of the fuel.
In MODE 3, 4, 5, or 6, this trip Function does not have to be OPERABLE because the reactor is not operating and there is insufficient heat production to be concerned about fuel overheating and fuel damage.
8.
Pressurizer Pressure The same sensors (PI-0455A, B, & C, PI-0456, PI-0456A, PI-0457, PI-0457A, PI-0458, PI-0458A) provide input to the Pressurizer Pressure - High and - Low trips and the Overtemperature AT trip.
Since the Pressurizer Pressure channels are also used to provide input to the Pressurizer Pressure Control System, the actuation logic must be able to withstand an input failure to (continued)
Vogtle Units 1 and 2 B 3.3-18a Revision No.
RTS fnstrumentation 8 3.3.1 i
BASES l
J j
l 4
THIS PAGE INTENTIONALLY LEFT BLANK.
l l
(continued)
Vogtle Units 1 and 2 B 3.3-18b Revision No.
o
I RTS Instrumentation B 3.3.1 BASES REFERENCES 2.
FSAR, Chapter 6.
(continued) 3.
FSAR, Chapter 15.
4.
5.
6.
WCAP-ll269, Westinghouse Setpoint Methodology for Protection Systems; as supplemented by:
Amendments 34 (Unit 1) and 14 (Unit 2), RTS Steam l
Generator Water Level - Low Low, ESFAS Turbine Trip and Feedwater Isolation SG Water Level - High High, and ESFAS AFW SG Water Level - Low Low.
Amendments 48 and 49 (Unit 1) and Amendments 27 and 28 (Unit 2), deletion of RTS Power Range l
Neutron Flux High Negative Rate Trip.
Amendments 60 (Unit 1) and 39 (Unit 2), RTS l
Overtemperature AT setpoint revision.
Amendments 57 (Unit 1) and 36 (Unit 2), RTS Overtemperature and Overpower AT time constants and Overtemperature AT setpoint.
Amendments 43 and 44 (Unit 1) and 23 and 24 (Unit 2), revised Overtemperature and Overpower AT trip setpoints and allowable values.
7.
WCAP-10271-P-A, Supplement 2, Rev. 1, June 1990.
8.
FSAR, Chapter 16.
9.
Westinghouse Letter GP-16696, November 5, 1997.
l l
{
l f
I l
Vogtle Units 1 and 2 B 3.3-60 Revision No.
l
\\
ESFAS Instrumentation B 3.3.2 BASES BACKGROUND Sianal Processino Eauioment (continued)
Generally, if a parameter is used for input to the SSPS and a control function, four channels with a two-out-of-four logic are sufficient to provide the required reliability and redundancy.
The circuit must be able to withstand both an input failure to the control system, which may then require the protection function actuation, and a single failure in the other channels providing the protection function actuation. Again, a single failure will neither cause nor prevent the prctection function actuation.
These requirements are described in IEEE-279-1971 (Ref. 4).
The actual number of channels required for each unit parameter is specified in Reference 2.
Trio Setooints and Allowable Values The Trip Setpoints are the nominal values at which the bistables are set. Any bistable is considered to be properly adjusted when the "as left" value is within the band for CHANNEL CALIBRATION tolerance.
l The Trip Setpoints used in the bistables are based on the analytical limits stated in Reference 2.
The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. To allow for calibration tolerances, instrumentation uncertainties, instrument drift, and severe environment errors for those ESFAS channels that must function in harsh environments t.s defined by 10 CFR 50.49 (Ref. 5), the Trip Setpoints and Allowable Values specified in Table 3.3.2-1 in the accompanying LC0 are conservatively adjusted with respect to the analytical limits.
The actual l
nominal Trip Setpoint entered into the bistable is more conservative than that specified by the Allowable Value to account for changes in random measurement errors detectable by a COT. One example of such a change in measurement error is drift during the surveillance interval.
If the measured setpoint does not exceed the Allowable Value, the bistable is considered OPERABLE.
(continued)
Vogtle Units 1 and 2 8 3.3-63 Revision No.
ESFAS Instrumentation B 3.3.2 BASES BACKGROUND Seouencer Outout Relays (continued) sequencer and are part of the control circuitry of these ESF loads. There are two independent trains of sequencers and each is powered by the respective train of 120-Vac ESF electrical power supply. The power supply for the output relays is the sequencer power supply. The applicable output relays are tested in the slave relay testing procedures, and in particular, in conjunction with the specific slave relay also required to actuate to energize the applicable ESF load.
APPLICABLE Each of the analyzed accidents can be detected by one or SAFETY ANALYSES, more ESFAS Functions. One of the ESFAS Functions is the LCO, AND primary actuation signal for that accident.
An ESFAS APPLICABILITY Function may be the primary actuation signal for more than one type of accident. An ESFAS Function may also be a secondary, or backup, actuation signal for one or more other accidents.
For example, Pressurizer Pressure - Low is a primary actuation signal for small loss of coolant accidents (LOCAs) and a backup actuation signal for steam line breaks (SLBs) outside containment.
Functions such as manual initiation, not specifically credited in the accident safety analysis, are qualitatively credited in the safety analysis r
and the NRC staff approved licensing basis for the unit.
These Functions may provide protection for conditions that do not require dynamic transient analysis to demonstrate Function performance.
These Functions may also serve as backups to Functions that were credited in the accident analysis (Ref. 3).
The LC0 requires all instrumentation performing an ESFAS Function to be OPERABLE.
Failure of any instrument renders the affected channel (s) inoperable and reduces the reliability of the affected Functions. The Nominal Trip Setpoint column is modified by a Note that requires the as-left conditions for a channel to be within the calibration tolerance for that channel.
In addition, the as-left condition may be more conservative than the specified Nominal Trip Setpoint. The conservative direction is established by the direction of the inequality applied to the Allowable Value.
It is consistent with the setpoint methodology for the as-left trip setpoint to be outside the calibration tolerance but in the conservative direction with respect to the Nominal Trip Setpoint.
(continued)
Vogtle Units 1 and 2 B 3.3-66 Revision No.
ESFAS Instrumentation B 3.3.2 BASES APPLICABLE The LCO generally requires OPERABILITY of four or three j
SAFETY ANALYSES, channels in each instrumentation function and two channels l
LCO, AND in each logic and manual initiation function.
The l
APPLICABILITY two-out-of-three and the two-out-of-four configurations i
(continued) allow one channel to be tripped during maintenance or testing without causing an ESFAS initiation.
If an instrument channel is equipped with installed bypass l
capability, such that no jumpers or lifted leads are l
l l
l i
(continued)
Vogtle Units 1 and 2 B 3.3-66a Revision No.
ESFAS Instrumentation B 3.3.2 BASES i
l l
THIS PAGE INTENTIONALLY LEFT BLANK l
l l
1 I
(continued)
Vogtle Units 1 and 2 B 3.3-66b Revision No.
ESFAS Instrumentation B 3.3.2 BASES SURVEILLANCE SR 3.3.2.8 (continued)
REQUIREMENTS verification of these devices every 18 months.
The 18 month Frequency is consistent with the typical refueling cycle and is based on unit operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.
This SR is modified by a Note that clarifies that the turbine driven AFW pump is tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 900 psig in the SGs.
SR 3.3.2.9 SR 3.3.2.9 is the performance of a TAD 0T as described in SR 3.3.2.6 for the P-4 Reactor Trip Interlock, and the Frequency is once per 18 months.
This Frequency is based on operating experience. The SR is modified by a note that excludes verification of setpoints during the TA00T.
The function tested has no associated setpoint.
REFERENCES 1.
FSAR, Chapter 6.
2.
FSAR, Chapter 7.
3.
FSAR, Chapter 15.
4.
5.
6.
WCAP-ll269, Westinghouse Setpoint Methodology for Protection Systems; as supplemented by:
Amendments 38 (Unit 1) and 18 (Unit 2), ESFAS Safety Injection Pressurizer - Low allowable value revision.
Amendments 34 (Unit 1) and 14 (Unit 2), RTS Steam Generator Water Level - Low Low, ESFAS Turbine Trip and Feedwater Isolation SG Water Level - High High, and ESFAS AFW SG Water Level - Low Low.
(continued)
Vogtle Units 1 and 2 8 3.3-109 Revision No. 4/98
\\
ESFAS Instrumentation B 3.3.2 BASES REFERENCES Amendments 43 and 44 (Unit 1) and 23 and 24 (Unit (continued) 2), revised ESFAS Interlocks Pressurizer P-11 trip setpoint and allowable value.
7.
WCAP-10271-P-A, Supplement 2, Rev. 1, June 1990.
8.
FSAR, Chapter 16.
9.
Westinghouse Letter GP-16696, November 5, 1997.
l 1
l l
l l
l I
l Vogtle Units 1 and 2 B 3.3-109a Revision No. 4/98
ESFAS Instrumentation 8 3.3.2 BASES i
THIS PAGE INTENTIONALLY LEFT BLANK.
1 I
l i
i i
i l
i l
l Vogtle Units 1 and 2 8 3.3-109b Revision No. 4/98 l