ML20042F251
| ML20042F251 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/25/1990 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20042F248 | List: |
| References | |
| NUDOCS 9005080051 | |
| Download: ML20042F251 (21) | |
Text
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LENCLOSURE1:.'
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PROPOSEDTTECHNICAliSPECIFICATION;-CHANGEJ 1
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TABLE 2.2-1 N
~
C REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS.
E Egk 21 h
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
[
- 1. Manual Reactor Trip Not Applicable' Not Applicable 2
27.V %
- 2. Power Range, Neutron Flux Low Setpoint - 5 25% of RATED Low Setpoint - < -26% of RATED H
THERMAL POWER TilERMAL POWER t
~
t//,Y %
High Setpoint - 5 109% of RATED High Setpoint 5-H9Tr-of RATED TilERMAL POWER THERMAL POWER
- 3. Power Range, Neutron Flux,
< 5% of RATED TiiERMAL POWER with
< 6.3% of RATED THERMAL POWER
"'8 liigh Positive Rate a time constant 1 2 seconds with a time constant 1 2 seconds
- 4. Power Range, Neutron Flux,
< 5% of RATED THERMAL POWER with
< 6.3% of RATED THERMAL POWER R48 liigh Negative Rate a time constant 1 2 seconds with a time constant 1 2 seconds
- 5. Intermediate Range, Neutron
< 25% of RATED TilERMAL POWER 5 30% of RATED THERMAL POWER Flux
- 6. Source Range, Neutron F1'ux 5 10 counts per second 5 1.3 x 105 counts per second 5
- 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT
..See Note 2 See Note /'f
/96V.8
- 9. Pressurizer Pressure--Low 1 1970 psig 14960 psig -
.2390.2
- 10. Pressurizer Pressure--liigh
< 2385.psig 5, M psig
- 11. Pressurizer Water level--High.5 92% of instrument span 5
f instrument span
,g c.
89.4 %
- ~89.17 Al '
i gx
- 12. Loss of Flow 190% of design: flow per loop
- 1-89% of. design flow per loop
- sn k?
- Design flow is 91,400 gpm per loop.
n
- -~
TABLE 2.2-1 (Continued) m REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS.
4 ZI FUNCTIONAL UNIT TRIP SETPOINT All0WABLE VALUES SE 12.4 'A
$ 21.
Turbine Impulse Chamber Pressure -
< 10% Turbine Impulse
< -HWr Turbine Impulse (P-13) Input to Low Power Reactor Trips Fressure Equivalent Pressure Equivalent Block P-7 y 59-2.,Al+
37.V %
22.
Power Range Neutron Flux - (P-8) Low
< 35% of RATED
< -3fA of RATED
[QllERMALPOWER Reactor Coolant Loop Flow, and Reactor TilERMAL POWER Trip 7.6 7o 23.
Power Range Neutron Flux - (P-10) -
> 10% of RATED
> -9%r of RATED Enable Block of Source, Intermediate, TilERMAL POWER TiiERMAL POWER and Power Range (10w setpoint) Reactor Trips 7
" 24.
Reactor Trip P-4
. Not Applicable Not Applicable SL C.
25.
Power Range Neutron Flux. - (P-9) -
< 50% of RATED
< M of RATED Blocks Reactor Trip for Turbine TilERMAL POWER Ti1ERMAL POWER Trip Below 50% Rated Power NOTATION-NOTE 1:
Overtemperature aT ( N< AT, [K - K 5)[T( M -T'J.+ K (P-P') - f (al)}
2(1+tga y
3 y
- +tS C+T5 y
4 l+ K5 iT ST 14=/-/g.
'< m I+551 yg where:
=+eg-compensator on measured AT 7
33 Bro Syp u
= Time constants utilized in the h $cE Itc-for AT,'.If 5'C5> 7 *3 *-
~
,r 4 s
2 e
r..-
AT,
= Indicated AT at. RATED TilERMAL POWER
'5 K
< 1.15 23 1
K,
= 0.011 L
- -. ~. _, -
a--.-.--
. =. _ - - - - -
TABLE 2.2-1'(Continued) m Eg REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Y
=
NOTATION (Continued)
E a
NOTE 2:
(Continued) i Time constant utilized in the rate-lag controller for T
= 10 secs.
T
=
pw Y3 STD
- avg,
)
- o3 deH.d in Mctc I ggde j.+ 7 3 f
q
- c dcf-ined in "ctc 1 4
K
=
6 0.0011 for T > T" and K = 0 for T $ T" W
6 O
T
=
as defined in Note 1 o
T"
= -Indicated T,yg at-RATED TilERMAL POWER (Calibration temperature for AT instrumentation, ; 578.2 F)
S as defined in Note 1
=
f (AI) 2 0 for all AI
=
NOTE 3:
The channel's' maximum trip setpoint shall not exceed..its computed trip point by more than f5'
-Zpercents sr sjmen.
1.9 by/. 2I o n
$ $ pors en Tie <kal.s.
mm.~~
f
,,1 a;,,F.,Lll sol ewal ib m/~U I'? /***"l A "C"
Y""
~
w, y
7 3
$y
' / 7pereen/ A 7" span.
g..
g y wore s: <-zusser ~z, -
km? RI T' b T
ubll ii niis i iii TABLE 4.3-1 (Continued) g REACTOR TRIP SYSTEl1 Iris 1 Rut 1ENTATIOf4 SURVEILLANCE REQUIREMENTS Q
CHANNEL H0 DES IN M11CH 3
CHANilEL CHANNEL FUNCTIONAL SURVEILLANCE 3
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED Dalehd 15.
Stecm/r cd.eatcr ric.; 'tizactch and S
n Q
1, 2 rM f3 g
Lc.. Stcc Ccncrator t!atcr Lcyci Z
16.
Undervoltage - Reactor Coolant N.A.
R gQ 1
Pumps 17.
Underfrequency - Reactor Coolant N.A.
R gQ 1
Pumps was. 70s 18.
=
A.
Low Fluid Oil Pressure N.A.
N.A.
S/U(1) 1 B.
Turbine Stop Valve Closure N.A.
N.A.
S/U(1) 1 19.
Safety Injection Input from ESF N.A.
N.A.
-M(4).R 1, 2 w
20.
Reactor Trip Breaker N.A.
N.A.
M(5) and S/U(1) 1, 2, and *
[
21.
Automatic Trip Logic N. A.
N.A.
M(5) 1, 2, and
- O 22.
Reactor Trip System Interlocks A.
Intermediate Range N.A.
R 4/U(0) N,/I, h
2, and
- Neutron Flux, P-6 B.
Power Range Neutron N.A.
-R- #. A.
S/"(0) NA.
L 1
Flux, P-7 C.
Power Range Neutron N.A.
R S/'.'(B) M4 1
Flux, P-8
).
D.
Power Range Neutron fl. A.
R _
{/L'(S) M4, 1, 2 Flux, P-10 E.
Turbine Impulse Chamber N.A.
R S/U(0)- M A-1
-G Pressure, P-13 h'{
F.
Power Range Neutron N.A.
R
-5/U(0) /V,//,
1 es-Flux, P-9 03 G.
Reactor Trip, P-4
'N.A.
N.A.
S/"(e) A 1, 2, and
- l R67 u"
F 23.
Reactor Trip Bypass Breaker N.A.
N.A.
M(10)R(11) 1, 2, and'*
R58 a
S
._= _.
TABLE 3.3-3 (Continued)
Mg ENGINEERED SAFETY FEATURE ACTUATION SYSTEM-INSTRUMENTATION O
E MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE
~
E FUtlCT10t1AL UNIT OF CilANNELS TO TRIP OPERABLE MCDES ACTION w
8.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS
~
a.
Pressurizer Pressure -
- 3 2
.2 1,2-3 22a
";i :' i: -P-1//ND7~ A'/pg9.T7 Al Neur a,f,y b.
', y g
- a. '~'
a' a'
^
^~
u
,e, etu c.
~ Steam Generator 3/ loop 2/ loop 3/ loop.
1, 2 22c Level P 14
=any loop w
a w
9.
AUTOMATIC SWITCHOVER T0 CONTAINi.ENT SUMP ca a.
RWST Level Low 4
'2 3
1, 2, 3,'4 18 R67-COINCIDENT WITH Containment-Sump
. Level
.High.
4 2'
3 1,
2,'.3, 4'
18 AND Safety Injection
[(See :1 -above for Safety Injection Requirements)
'b.
Automatic Actuation
= 2.
- 1-21 1,.2, 3,'4L.
-15 R67
~
py
' Log ic --
'E@
s a.
. g -.
t=
.. o 3
.i s.
~'
s TABLE 3.3-4 (Continued)
M E
EflGIf1EERED SAFETY FEATURE ACTUATf0f1 SYSTEM IfiSTRUMEf1TATIOff TRIP SETPOINTS
?
FUflCII0flAL Uf11T TRIP SETPOI!1T ALLOWABLE VALUES
/7.
LOSS OF P0h'ER z;
a.
6.9 kv Shutdown Board Undervoltage Loss of Voltage 1.
Start.of Diesel Generators R33 a.
flominal Voltage Setpoint 4860.>olts 4860 volts +97.2 volts b.
Relay Response Time for 0 volts with a 1.5 second 0 volts witE a 1.5 +0.5 Loss of Voltage time delay second time delay 2.
Load Shedding a.
flominal Voltage Setpoint 4860 volts 4860 volts + 97.2 volts b.
Relay Response Time for 0 volts with a 5.0 second 0 volts with a 5.0 +1.0 t'
Loss of Voltage time delay second time delay -
u b.
6.9 kv Shutdown Board-Degraded w
4 Voltage w'
1.
Voltage Sensors 6560 volts 6560 volts + 33 volts
- 2.
Diesel Generator Start and Load Shed Timer 300 seconds
'300 seconds + 30 seconds 3.
SI/ Degraded Voltage Logic Enable Timer 10 seconds 10 seconds + 0.5 seconds 8.
LilGIllEERED SAFETY FEATURE l
ACTUATI0fl SYSTEll IllTERLOCKS.
a.
Pressurizer Pressure 1975.a 6j/e b EF
!!2~ ?! 9!}^fu/ canal:e 4 ef Safetl" !r ection "
~< 1970 psig
-< 49es-psig i
d b/cel e/ Jadij 2e.
la Nor b In t re *Ny Ae's"'e Q
g.g sayes e en 89-27 Af o
ev
_4 r i t -
n:, t g..,3cp specitj atjen_4,; te he 59%%t_
437 tup re?!ceing the 7p,# reggm!!ng
~
me-rown =vlae=v or u= nww.swn i; wrun -
.g u
w f-// ' [osa$c ~ /Yla$nal Blotl el h h.
A, 3
xy, e-.., n,:, it,,,
M'te r i m. *,,i,
m u
s
.._f
...--...o-w-wm
TABLE 3.3-4 (Continued)
Ng EllGItlEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Se 7
FullCTIO!!AL UtlIT TRIP SETPOINT ALLOWABLE VALUES E
8.
EllGillEERED SAFETY FEATURE ACTUATIOil C
SYSTEf1 IllTERLOCKS (Continued)
~
b.
D fald
-Preecnt: ":nua! B1cck cf Safety j.5lB Injecticr P-12
- 510 F 1 512*F s
Q DcLU c.
";rual Block of Safety Injection,
-Stear Lin I;clation, Bloch Stec-De p u
__ 5?O F
-. 53B"r s
A w
d.
Steam Generator Level 4
Turbine Trip, Feedwater Isolation P-14 (See 5. above) 9.
AUTOMATIC SWITCH 0VER TO CONTAltlMEllT sui 1P
.e-69-27 p/
R67 2 7/
a.
RWST Level - Low 130" from tank base 130" i f from tank base COINCIDENT Willi f,fJ "
Containment Sump Level '- liigh 30".above elev. 680' 30" 1 Jd!" above elev. 680'
- Afl0 '
n{
Safety Injection.
(See 1:above for all: Safety Injection Setpoints/ Allowable Valves) s o a
' E&
b.
A' omatic Actuation logic.
N.A.
H.A.
. w-1*
OC 0 fosse w ns h n h u f g' d sk
.jk ; co,e hoher ko Aa,s.. to o,,
x2n ><..A s s/- K & j~ seco w l,.
ub7 ASb A '
T*,ne wvlne/ e$*$sd ss*,
sab-b _ ta,sbv/be.' b Ahnd*<< ~Slambe Aw-w Asd -// $
k
'f e f
)
i.s 7? 50.seco,ad.
r cw,-
c.=---
.ptw,'-~
y i-y-y
.y
...y,.,,
,s-%
,s 3
.9 et a
.u.
3 s
N
~
TABLE 4.3-2 (Continued)
E Ef!Gif1EEllED SAFETY FEATURE 'ACTUATI0ff SYSTft! If1STRUffEllTATION S'
SURVEILt AtJCE REQUIREfittelS 5'
CllANNEL t10 DES IN WillCil c
CilAfif1EL CllAfillEL FUf1CTIONAL SURVEILLANCE
}
FUtlCTICilAL UtlIT CllECK CALIBRATIOff TEST REQUIRED d.
6.9 kv Shutdown Board -
Degraded Voltage 1.
Voltage sensors S
R 1, 2, 3, 4 R33 2.
Diesel Generators it. A.
R fl. A.
1, 2, 3, 4 Start and Load Shedding Timer 3.
SI/ Degraded Voltage it. A.
R fl. A.
1, 2, 3, 4 t'
Logic Timer u
Y 8.
Ef1GIllEERED SAFETY FEATURE y
ACTUATI0ff SYSTEl-1 IllIERLOCKS[gg.yyg/
I a.
Pressurizer Pressure,
. fl. A.
R(2) fl. A.
1, 2, 3 P-11/NOT / //
RSI A
flea / MO I
b.
"^
'avo' c.
Ste m Generator fl. A.
R(2) fl. A.
1, 2 Leve,.P-14 fi' 9.
AUT0ilATIC SWITCl10VER'TO 2g C0fl1AIllilEllT SullP
,e 69-27A i SE 32 a.
f<5WI I evel - Lou S.
.R
-M-Q 1, 2, 3, 4
,7 COIllCIDEllT Willi Fif Containment Sump level - liigh S
R 4Q 1, 2, 3, 4 AllD
{t Safety. Injection (See I above f or all Safety Injection. Surveillance. Requirements) 1;.
Automatic Actuation Logic fl. A.
fl. A.
Ff(I) 1, 2, 3, 4 R67 5
14410:
this techr, ice! specif! Eat-ion-4e-be--imp!crented ::t the startup fe!!cs!ug the 2M r"f u=!!ng outaga
-Gr-54140ving-somydeMen-e! t!:c ~:di fisaMen&ishever is car'ier.
E w
s._.,
-, - - _ - - ~ -. -
.N -.
'~
TABLE 2.2-1 N
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E!
E FUNCTIONAL UNIT TRIF SETPOINT ALLOWABLE VALUES
- 1. Manual Reactor Trip Not Applicable Not Applicable 4 2 Y 7.
- 2. Power Range, Neutron Flux Low Setpoint - < 25% of RATED Low Setpoint - <-26% of. RATED THERMAL POWER -
THERMAL POWER ~
III.1 %
High Setpoint - < 109% of RATED THERMAL POWER- -
High Setpoint
<-140% of RATED -
THERMAL POWER
- 3. Power. Range, Neutron Flux,
< 5% of RATED THERMAL POWER with
< 6.3% of RATED THERMAL POWER High Positive Rate a time constant 1 2 seconds with a time constant 1 2 seconds R36
- 4. Power Range, Neutron Flux, 5 5% of RATED THERMAL POWER with 5 6.3% of RATED THERMAL POWER R36 High Negative ~a a time constant 1 2 seconds with a time constant > 2 seconds m
c5
- 5. Intermediate Range, Neutron 5 25% of RATED THERMAL POWER
< 30% of RATED THERMAL POWER Flux
- 6. Source Range, Neutron Flux
$ 105' counts per.second 5
< 1.3 x 10 counts per second
- 7. Overtemperature AT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note J'/
194V.s
- 9. Pressurizer Pressure--Low 1 1970 psig 1-1960 psig 2 3 7 0. a.
- 10. Pressiirizer Pressure--High 1 2385 psig 5 ii'395-psig 92.2 %
- ~
p
- 11. Pressurizer Water Level--High 5 92% of instrument span
< 0%r of instrument span G$
- 89A7, mg
- 12. Loss of Flow 2 90% of design flow 2 69% of design' flow e-69.274/
,g
- per loop *
=
per loop
- 5 E2
^0esign flow is 91,400 gpm per loop.
- o e
.a-n>.-n.>.
-_.e axwn-
---.w
.....~,..,w
.ae.sm.
... _. A Am
E
~
TABLE 2.2-1 (Continued) m g
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Y
z FUNCTIONAL UAIT TRIP SETPOINT ALLOWABLE VALUES g
/2.4 %
7 21.
Turbine Impulse Chamber Pressure -
< 10% Turbine Impulse
<-H% Turbine Impulse (P-13) Input to Low Power Reactor Trips Pressure Equivalent Pressure Equivalent g
Block P-7 37y7 C E9-2 7 R t.
22.
Power Range Neutron Flux - (P-8) Low
< 35% of RATED
< -3fA of RATED Reactor Coolant Loop Flow, and THERMAL POWER THERMAL POWER Reactor Trip
~1. & *7.
23.
Power Range Neutron Flux - (P-10) -
> 10% of RATED
> M of RATED Enable block of Source, Intermediate, TiiEl: MAL POWER THERMAL POWER and Power Range (10w setpoint) reactor Trips 2
24.
Reactor Trip P-4 Not Applicable Not Applicable 52 1 %
25.
Power Range Neutron Flux - (P-9) -
< 50% of RATED
< -51% of RATED Blocks Reactor Trip for Turbine TilERMAL POWER -
THERMAL POWER Trip Below 50% Rated Power
',[ --
NOTATION Overtemperature AT ( M _< AT,'[K NOTE 1:
2 (I + r
)[T(
T'] + K (P-P') - f (AI)]
-K y
~3 y
G+tS f+T 5 y
4 D
x g where:
p 7 3 = Lag compensator on measured AT I
led.Q ab,Ilea g 2.
g 7,
= Time ~ constants utilized in the -hg cc ;;m:te-for AT, T = 2 secs, 7 = J aus.
r r
- f Af,
= Indicated AT at RATED TiiERMAL POWER.
[
.K
< 1.15 y
R21 g-K
= 0.011 2
e
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP'SETPOINTS "E
NOTATION (Continued)
EZ NOTE 2:
(Continued)
Time constant utilized in the rate-lag controller for T,yg, ty = 10 secs.
T
=
I defined ia Note -
= ac
.i *I4) r
- c defined i-Mete-4--
4 R 21 K
=
0.0011 for T > T" and K6 = 0 for T i T" 6
m O
T
=
as defined in Note 1 o
T" Indicated T,yg at RATED THERMAL POWER-(Calibration temperature for
=
AT instrumentation, 5 578.2 F)
S as defined in Note 1
=
~
f (AI)
= 0 for all AI 2
NOTE 3: The channel's maximum trip setpoint shall not' exceed its computed trip point by more than g
Z'percentx s T span, e
cn 49 g,
rn ll NOTE 4: T h e e b.,,,,/'s
,,mi,,ua )f.sa-/ o:.,1-4a//
,,o/ ana;,/ t/s to,ysL / 4 y.sc /p ai. f-b p
y 6 1,7 pen, f-e inoa
. spa n,
if iB8 A'DTE S: +.T,,u,}
6 "
$947 gl
- -..... ~.. - _ _ -,. _.. -. _..
TABLE 4.3-1 (Continued)
]m
. REACTOR TRIP SYSTEM INSTRUi1ENTATION SURVEILLANCE REQUIREffENTS E
5 Cl!ANNEL 110 DES FOR WilICil CilANNEL CilANNEL FUNCT10NAL SURVEILLANCE IS-7 FUNCTIONAL UNIT CllECK CAllBRATION TEST REQUIRED gy c
- 15. -Steam /feedwater410w-Mismatch and S
-tcu Ste r Cencrater W ter Lc/c!
Q 1, 2 R16 ro 16.
Undervoltage - Reactor Coolant N.A.
R WR 1
Pumps 17.
Underfrequency - Reactor Coolant N.A.
R
,M' S 1
Pumps 18.
Turbine Trip A.
Low Fluid Oil Pressure N.A.
N.A.
S/U(1) 1 B.
Turbine Stop Valve Closure N.A.
N.A S/U(1) 1 R
19.
Safety Injection Input from ESF N.A.
N.A.
MR 1, 2 w
20.
Reactor Trip Breaker N.A.
N.A.
M(5) and S/U(I) 1, 2, and
- M 21.
Automatic Trip Logic N.A.
N.A.
M(5) 1, 2, and
- 22.
Reactor Trip System Interlocks A.
Intermediate Range N.A R
-5/U (3} Md.
2, and
- Neutron Flux, P-6 B.
Power Range Neutron N.A.
-R-- N. A.
S/U (0) MA.
t1 Flux, P-7 C.
Power Range Neutron-N. A.
R S/U ( G ; N.d.
1 Flux, P -
D.
Power Range Neutron N.A.
R i
S/U (U) NJ.
- 1. 2 FF Flux, P-10 1
2@
E.
Turbine Impulse Chamber N.A.
R
- g. &
Pressure, P-13 i'U ( O r,64, I
8 F.
Power Range Neutron a
Flux, P-9 N.A.
R Q/U (3) MA, 1
v.~ E G.
Reactor Trip, P-4 N.A.
N.A.
-t / " ( 3 1 /t
. I, 2, and *
$55
- ~
23.
Reactor Trip Bypass Breaker.
N.A.
N.A.
M(10)R(11) 1, 2, and
- 3.*
gg s
- m.
_.,n_was+~#--=---."*#'
M TABLE 3.3-3 (Continued) e S!
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRIR-!ENTATIOff E
HitlIMUM c
TOTAL NO.
CHAf1TIELS CliANNELS APPLICABLE FUNCTIONAL UNIT z
OF CHAftttELS TO TRIP OPERABIE MODES ACTIOff m
8.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM ItiTERLOCKS a.
Pressurizer Pressure -
3 2
2 1,2,3 22a 39-27Af a -Net P-11/#T P-U Da LI.J b.
-T
- P-12 avg 2
3 I, 2, 3 224:
c.
Steam C-enerator 3/ loop 2/ loop 3/ loop 1, 2 22c y
Level P-14 any loop-u w
9.
AUTOMATIC SWITCHOVER TO CONTAINMENT SUMP o
a.
RWST Level - Low 4
2 3
1, 2, 3, 4 18 f55 COINC 9ENT WITH Conttiaznt Sump Lew. - High 4
2 3
1,2,3,4 18 AND Safety Injection (See 1 above for Safety Injection Requirements) o b.
Automatic Actuation 2
1 2
1, 2, 3, 4 15 gN Logic
!i E g35 b-g "B
m-728 G~
3.=
M
a D
s la s
s u
5 0
d d
ll s
s n
n i.
t0 t1 s
o o
l 1
l 1
t c
c e
lo o
l e
e u
v5 y
v 0. y o
s s
f v
m S
21 a 25a 0
5 L
l l
l 3
f i
7 ae iae
'i t
J-i l
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i SEQUOYAH - UNIT 2 3/4 3-28 Amendment No. 5.
55 December 31, 1987 i
r
I TABLE _4.3-2 (Continued) m5g EllGIffEERED SAFETY FEATURE ACTUATI0ff SYSTEM IriSTRUMENTATIOff g
SURVLILLAtlCE REQlilREMLflI5
=
~
s CHANNEL MODES FOR Wi!ICil c
CilANNEL CilAntJEL FUNCTIONAL SURVEILLANCE IS 5
FUNCTI0flAL Ut4IT CHECK CALIBRATI0ft TEST REQUIRED w
M.
6.9 kv Shutdown Board -
Degraded Voltage 1.
Voltage sensors S
R H
1, 2, 3, 4 2.
Diesel Generators N.A.
R N.A.
1, 2, 3, 4 Start and Load Shedding Timer 3.
SI/ Degraded Voltage N.A.
R fl. A.
1, 2, 3, 4
{
logic Timer T
8.
EllGINEERED SAFETY FEATURE M
ACTUATION SYSTEM INTERLOCKS a.
Pressurizer Pressure, N.A.
R(2) fl. A.
1, 2, 3 927Al P-11/Nor P-tj b.
T
!?
"^
9(2) 1, 2, 3
"^
gy c.
Steam Generator N.A.
R(2)
N.A.
1, 2 Level, P-14 E>
- 2 9.
AUTOMATIC SWITC110VER TO
?E CONTAINMENT SUMP s
a.
RSWT Level - Low 5
R
.W Q 1, 2, 3, 4 COINCIDENT WITH
-E Containment Sump Level - liigh 5
R Jt-Q I, 2, 3, 4 f
Atto QM Safety Injection (See I above for all Safety Injection Surveillance Requirewents) u, b.
Automatic Actuation Logic fl. A.
II. A 11( 1 )
I, 2, 3, 4
- W>
vs C.
MtMl+iS-leEh6IEal ";p0Cififat400--i-9 LO SC i g IC;;:_^iittd ? T I ;j' the S ta -t uj: f0?'O d M4f-4fr' ? t t ""^ ! " ? ' E ""j "'!.',"'-
- C-gg3 s'
ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-89-21)
DESCRIPTION AND JUSTIFICATION FOR REVISION TO TS 89-27
/
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ENCLOSURE 2 Description of Change Tennessee Valley Authority proposes to revise the Sequoyah Nuclear Plant (SQN) Units 1 and 2 Technical Specification (TS) Change 89-27, submitted January 24, 1990.
Specifically,thefo} lowing-revisionsaremade.
1.
The reactor coolant system (RCS) loss of flow (Table 2.2-1,-Item 12) allowable value is revised.
2.
The low RCS flow reactor trip permissive, P-8 (Table 2.2-1 Item'22)~
nominal setpoint and allowable value are revised.
3.
The overpower delta-T maximum trip setpoint (Table 2.2-1,_ Note 4)'is revised.
4 4.
The channel functional test frequency notation for_ reactor trip system interlocks (Table 4.3-1, Item 22) that have refueling outage frequency channel calibrations are revised.
S.
The pressurizer pressure safety injection block permissive, P-11 entries (Table 3.3-3, 3.3-4, and 4,3-2, Item 8.a) are revised.
6.
The automatic switchover to containment sump (Tables 3.3-4 and 4.3-2..
1 Item 9.a) contal; nent sump and-refueling water storage tank- (RWST) level allowable values and channel functional test Intervals are revised.
1 Reason and Justification for Change Changes I, 2, and 3 are made for consistency with the issued Eagle 21 setpoint methodology.
TS 89-27 was submitted in parallel with the issuance of the final setpoint methodology, and the corresponding _ values were changed as the result of the ongoing review by TVA and Wastinghouse.
Change 4 is made to remove redundant and unnecessary information from TSs. TS Definition 1.4 states that a cLannel calibration shall include a l
channel functional test.
Therefore, for functional items that are~
calibrated on a refueling outage frequency, the notation of'a refueling outage frequency channel functional test does not provide any useful H
information. Consequently, the channel functional test notation for functional Items 22.A, 22.C. 22.D, 22.E. and 22.F is revised to "N.A."-
This combination of calibration and functional test notation is consistent with the testing requiremcnts for the loss'of RCS flow in.two loops reactor trip (lable 4.3-1 Item'13).
Change 5 is made to clearly identify both the trip and reset functions of the P-11 safety injection permissive.
Inclusion of the P-11 block enable setpoint and allowabic value is warranted because the negative steamline pressure rate steamline isolation function is enabled.when safety s
i i
y
[
d
- injection is manually blocked below 1,970 pounds per square inch gauge (psig).
The difference between the P-11 block enable setpoint and allowable value represents a rack drift allowance, and is the same magnitude as that of the NOT-P-11 automatic unblock.
The margin between d
the P-11 and NOT-P-11 setpoints reflect a one percent deadband to prevent i
" chattering" of the permissive.- The changes to the entry titles for the l
P-11 permissive are editorial in nature and are made for clarification.
Change 6 is made to reflect the improved rack drift term associated with-l the Eagle 21 system for the containment. sump and RHST level channels.
As j
indicated in~the Eagle 21 setpoint methodology, the calculation of these allowable values was not within the scope of work being performed by Westinghouse. TVA has completed the instrument accuracy calculations;for' the containment sump and.RHST level channels, and these calculations'are_
_i provided as Enclosure 3 to this letter.. The. rack-drift terms for these channels are consistent with those in the Eagle 21 setpoint methodology, 0.7 percent of calibrated span (reference Sheet 20 of Calculation.
TI 28-0013, containment sump; and Sheet 17 of Calculation TI 0015, 9
RHST). The calibrated span of the containment sump level channels is 0 to 240 inches (TI 28-0013, Sheet'12), which yields a rack-drift term of plus or minus 1.68 inches.
This in turn is applied to the nominal-setpoint for an allowable-value of 30 plus or minus 1.68 inches.
Similarly, the calibrated span of the RHST level channels is 0 to 387 inches (TI 28-0015, Sheet 11), resulting in a rack-drif t. term of plus or minus 2.71 inches, and allowable value of 130 plus or minus 2.71-inches.
The channel functional test entries for the containment sump and RWST level channels are revised for consistency with other channels that are processed by Eagle 21 and calibrated on a refueling outage frequency.
In summary, the revisions to TS 89-27 described above are made:to prosiae an accurate reflection of the SQN reactor protection system after implementation of the Eagle 21 upgrade.
The numerical revisions provide standard consistency with Eagle 21 setpoint methodology.
The= text changes a
provide clarity and remove redundant information-form the TSs.
As such,-
the revisions do not alter the conclusions drawn in the enviror. mental impact evaluation or the no significant hazards consideration submitted with TS 89-27.
- ~-
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u b.:
sQ
,u
'i s
ENCLOSURE 3 i
a TVA CALCULATION-TI28-0013, CONTAI'NNENT SUMP LEVEL CHANNELS
.1
- (887 900402:012)
-TVA CALCULATION TI28-0013. REFUELING HATER STORAGE TANK:(RWST)! LEVEL CHANNELS:
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