ML20069K285
ML20069K285 | |
Person / Time | |
---|---|
Site: | Farley |
Issue date: | 06/10/1994 |
From: | SOUTHERN NUCLEAR OPERATING CO. |
To: | |
Shared Package | |
ML19304C251 | List: |
References | |
NUDOCS 9406150354 | |
Download: ML20069K285 (15) | |
Text
.
FNP Unit 1 Technical Specifications Changed Pages Unit 1 Revision Page 2-6 Replace Page 3/4 3-27 Replace Page 3/4 3-28 Replace l
l l
l l
l 9406150354 940610 PDR ADOCK 05000340 P PDR
4i ,f: '! l$';l ! i! { !t , l ." (t I! ', [! i l
_ t n
e
- m _
u r
t _
sr no i t a
er ge s
u nn b ae rg s
h u c b S
wm oa a
e h E re c
. U rt - a e e e L as e l l l S A n s b b b T V h t - a a a N f c l c c c I E oa o z g i i i O L e - v H i l l l P B % - s p p p T
E S
A W
O 3
3 n 0
4 6
9 6
3 p
A p
A p
A p
L 2 ap - 2 5 4 t t t P L - o o o I A 2s - 2 2 2 N N N R
) T d N e O u I n T i
t A n T o N E
C M s
I U
h u R ec ga b
1 T s S ne a
h c
u 2
N b I r- a 2 e h E M wnr oao -
c a e e e L E T rpt e l l l B T N rsa r s b b b A S I a t - a a a T Y O nt e l c c c S P nn o g i i i P T E
f ee-omg- v H i l p
l p
l p
I s R
S u - 0 0 p p p p T % rm- 8 A A A P 5t a- 6 7 5 R
I 2 se- 2 5 4 t t t O
R nt - o o o T T 2is- 2 2 2 N N N C
A E
R r t r o e u p e t v p pi t c l n mr a a a I uT W e V P R p n n r t o p o t o ow t o s
yn ca t o i ni t at aL ep nl p S t S c li T r- gm eo i oe e os I ew no au uo qC rt ree j oo N tP Tuunr n CP U eL l e IF G - d ot rr e Asiu sbs S rr
. L ml
- e vn ra f o nwero yE oe A t rt s iorul t tk N ae ev e el ecp br LPTC em ca O l do dam f o ae I t e e no neu u . .
ar er T SL D UC URP TA B Sf RB C
N . . . . . . .
U 3 4 5 6 7 8 9 F 1 1 1 1 1 1 1
)xrM<gzy . gr* >zmZozh4 =0 *
! j
< f ,!, }[ ;! ;' ![! ;' ,.i',L, l -
t n aF w0
% e -
4 enyoo4 4 wel tl5 e S thr f g _
T oetag 2 n -
N I
d e:
tb enm dnia g ah rc O nsgwnide v a .
P T S i wnoal nt a f oil osT we o
E E e e eldfdgp rnr S U dl n anslh rao L l l oomoiel t apt P A V
b a
b a
nf pal srui se nsa r I g o arf w R c c i iset% eo g f te T E i i s t ars0 rcfd i onn L l l p c r 2 c oa s ee N B p p ndol np o p % mg O A p p 5 uecldiA%l 5 u I
T W
O a A 7
. f n un i pf apa 5
.l 5
7
.rm 0t a -
A L t t 1 AfA A 1l 5 8 se T L o o e f% o1 u nt N A N N $ 5dAo0 at1f 2 5is E
M U
) R d T po e e S g u N o At o n n I d t t ah i e day rc t M n g n l gm a n
o E
T i
f nmanrnad i a e a i e a *F we o
C S e e e de%hedt o3 rnr
(
Y d nt0t nnsl4 rao S T l l os io 5 apt N n p nsar 4 b b ndl pll .
- N I a a g o: sl en sll2 -
3 O O c c i i sel eageuu g ft e _
. I P i i s t wruw nrff g i v
onn 3 T T E
l p
l p
p corf tdir s ee A nl o easof t a p % mg E U S p p 2 ul cfboacoaT u L T P
A A . f o f p o l e rp% wh 5 2. r m B C 6 w 8 9t a A A I t t 1 A A% o% cA0 ot 5 7 se T R o o s 0l0 n 1li nt E T N N 5 5aA4f2i a1f w 2 5is R
U T
A E
F w V
o R
- L E T - - T r E e - A e F n r e W t A o u ,
r a S i s oh u D W N t s wg' s E h D O a e Tih s E rg E I u r Ht e F oi R T t P niw r tH E
E A A
c i wo P D a-N L t s L N rh O n wet - e_ A eg I
G S
I i c eh mg onnw li eo i n
P ni eH N T t ni FLdL L I 'G -
E I E l a iH i- R -
N U
N I
a u
mc oi a-th mmc-aang m a
TN O
ml ae L n t g ng eeiv e EI ev L a uo oi tt oa t FT t e A M M AL CH SSCT S I A SL N A BL O E RO I T . . . . .
US .
T S a b c d e TI a C
N U . .
F 4 5 M>O*'MY$ h -
't R^ yw" j
@ yEEMZ3-
- 0.
1 ii'\ :< iI : al ,} , 1
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS m
W FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E
7 6. AUXILIARY FEEDWATER C
Z y a. Automatic Actuation N.A. N.A.
Logic
- b. Steam Generator Water 2 25% of narrow range 2 23.3% of narrow range l Level--Low-Low instrument span each instrument span each steam steam generator generator l
- c. Undervoltage - RCP 2 2680 volts 2 2640 volts
- d. S.I. See 1 above (all SI I setpoints)
- e. Trip of Main Feedwater N.A. N.A.
Pumps
- 7. LOSS OF POWER w
- a. 4.16 kv Emergency Bus 2 3255 volts bus 2 3222 volts bus voltage w Undervoltage (Loss of voltage
- 5 3418 volts bus voltage *
/o Voltage) m
- b. 4.16 kv Emergency Bus 2 3675 volts bus 2 3638 volts bus voltage" Undervoltage (Degraded voltage 5 3749 volts bus voltage Voltage) 1 8. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS
$ a. Pressurizer Pressure, P-11 5 2000 psig 5 2010 psig m
Z
- g b. Low-Low Tavg, P-12
$ (Increasing) 544*F 5 547 F
% (Decreasing) 543 F 2 540*F l Z i o c. Steam Generator Level, P-14 (See 5. above) i
- d. Reactor Trip, P-4 N.A. N.A.
Refer to appropriate relay setting sheet calibration requirements.
TABLE 2.2-1 (Continued) b
' REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT 1 125%
Att0WABLE VALUES z
Z 13. Steam Generator Water
^
%3%
of narrow range instrument Level--Low - Low span - each steam generator narrow range instrument l
- sp each steam generator
- 14. Deleted i
- 15. Undervoltage - Reactor Coolant Pumps 2 2680 volts - each bus 2 2640 volts - each bus
- 16. Underfrequency - Reactor Coolant Pumps 2 57.0 Hz - each bus 2 56.9 HZ - each bus
- 17. Turbine Trip A. Low Auto Stop 2 45 psig m Pressure 2 43 psig i B. Turbine Stop Valve Not Applicable
- o. Closure Not Applicable
- 18. Safety Injection Input Not Applicable from ESF Not Applicable
- 19. Reactor Coolant Pump Not Applicable Breaker Position Trip Not Applicable 9
Si!
9 E
h
m 5;
- TABLE 3.3-4 (Continued)
I g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS M
FUNCTIONAL UNIT TRIP SETPOIfff ALLOVABLE VALUES
- 4. STEAM LINE ISOLATION
- a. Manual Not Applicable Not Applicable
- b. Automatic Actuation Not Applicable Not Applicable Logic
- c. Containment Pressure-- 5 16.2 psig f 17.5 psig l y High-High n
- d. Steam Flow in Two Steam < A function defined as follows: < A function defined as follows:
Y Lines--High, Coincident E op corresponding to 40% of full A op corresponding to 44% of full O vith T --Lov-Lov steam flow between 0% and 20% load steam flow between 0% and 20% load and then a op increasing linearly and then a op increasing linearly to a op corresponding to 110% of to a op corresponding to 111.5% of full steam flow at full load with full steam flow at full load with T,,, 1 543*F T,,, 1 540'F
- e. Steam Line Pressure--Lov 2 585 psig 1 575 psig
- 5. TURBINE TRIP AND FEED WATER ISOLATION 792b gg,gg,
- a. Steam Generator Vater 5- f narrow range instrument f f narrow range instrument
$ Level--High-High span each steam generator span each steam generator E
e m
5
IABLL 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOI FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 7 6. AUXILIARY FEEDWATER E a. Automatic Actuation N.A. N.A.
2 59
- b. Stea::: Generator Water 2 (5$3 f narrow range instrument @. J narrow range instrument l Level--Low-Low s ch steam generator span Tach steam generator
- c. Undervoltage - RCP 2 2680 volts 2 2640 volts
- d. S. I.
See I above (all SI setpoints)
- e. Trip of Main feedwater N.A.
Pumps H.A.
{ 7. LOSS OF POWER
- a. 4.16 kv Emergency Bus 2 3255 volts bus voltage
- Undervoltage (Loss of Voltage) 2 3222 volts bus voltage
- co s 3418 volts bus voltage *
- b. 4.16 kv Emergency Bus 2 3675 volts bus voltage
- Undervoltage (Degraded Voltage) 2 3638 volts hus voltage
- s 3749 volts bus voltage *
- 8. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS
- a. Pressurizer Pressure, s 2000 psig P-11 s 2010 psig
% b. Low-Low T , P-12 z (Increasing) 544*F
% (Decreasing) s 547 F 543 F 2 540 F
- i z c. Steam Generator Level, P P-14 (See 5. Above) 2; .* d. Reactor Trip, P-4 N.A.
- % N.A.
'y
- Refer to appropriate relay setting sheet calibration requirements.
1 FNP Unit 2 Technical Specifications Changed Pages Unit 2 Revision Page 2-6 Replace Page 3/4 3-27 Replace Page 3/4 3-28 Replace I
1
f ;;! ;[ ;i i r ! j ti", ' ; ' i:f ifiii , l(:
l i ,
[ , _
. l _
t n
e m
u r
t _
sr _
no i t _
a _
- er ge s
u nn ae b s
rg h u
. c b S
wm oa a
e h E re c U rt - a e e e L
A as e l l l S n s b b b T V h t - a a a N f c l c c c I E oae o z g i i i O L - v H i l p
l p
l p
P B % - s T
E S
A W
O 3
3 n 0
4 6
9 6
3 p
A p
A p
A p
L 2 a - 2 5 4 t t t P L p - o o o I A 2s - 2 2 2 N N N R
) T d N e O u I n T i
t A n T o N c E s
( M h u U ec b 1 R ga s T ne h u S a 2
N c b I r- a 2 e h E M wnr oao -
c a e e e L E T rpt e l l l B T N rsa r s b b b A S I a t - a a a T Y O nt e l c c c S P nn o z g i i i P T E
f ee-omg- v H i l p
l l I s p p R
S u - 0 0 p p p p T % rm- 8 .
A A A _
P 5t a- 6 7 5 I 2 se- 2 5 4 t t t R R nt - o o o _
O T T 2is- 2 2 2 N N N _
C _
A _
E _
R r t _
r o e u p _
e t v p pi t
a c
a l n mr a I uT W e V P R p n n r t o p o t o ow t o s
yn ca t o i ni t at aL ep nl p S t S c li T r- gm eo i oe e os I
N ew no au uo qC rt ree j oo tP Tuunr n CP U eL l e IF rr e Asiu G - d ot sbs S rr L
A ml t
e vn ra f o rt s n wero iorul yE t
oe tk N ae e el ecp br LPTC em ca
. O ev l do dam f o ae I t e e no neu u. . ar er T SL D UC URP TA B Sf RB C
. N . . . . . . .
U 3 4 5 6 7 8 9 F 1 1 1 1 1 1 1 3xem<gZ y u g - "' Da GZmZH Zo-
.{4; i.* j
i ,* : ' !j;ll l , !l ,;il! l' l
- { fl ' j j , :f[ t!i t l -
t n aF
% e w0 4 enyoo4 4 wel tl5 e S thr f g T oet ag 2 n -
N d tb enm ah I e:
n s g w nid e v dnia g rca O
P T S i wnoal nt a f oil osT we o
E E eldfdgp rnr S U e e dl n anslh rao L l l oomoiel t apt -
P I
A V
b a
b a g nf pal srui o se arf w nsar -
R c c i i set % eo g f t e T E i i s t ars0 rcfd oa i onn ee c
L l l p r 2 c s -
N B p p ndol np o p % mg O A p p 5 uecldiA%l 5 u -
I T
W O
a A 7
. f n ipf apa un 5
.l 5
7
.rm 0 t a A L t t 1 AfA A 1l 5 8 se T L o o e f% o1 u nt I
A N N 5 5dAo0 at1f 2 5is D
M -
U
) R d T po e
e S g u N o At o n -
n I d t t ah .
i e day rc t M n g n l gm a n E i nmanrnad F we o
o T f i a eaiea C S e e e de%hedt o3 nt0 t nnsl4 rnr rao
(
Y d S T l l os i o 5 apt 4 N b a
b a g n
o: sl en p ndl pll sll2 nsar _
- N I _
3 O O c c i i sel eageuu g f t e .
. I P T
i i s p
t wruw corf tdir nrff g i v
onn ee 3 T E l
p l
p s
% mg A nl o easoft a p E U S p p 2 ul cfboacoaT u L
B T
C P A A 6
f o f p o
w l e rp% wh 5
8 2
9t a rm A A I t t 1 A A% o% cA0 ot 5 7 se T R o o s 0l0 n 1li nt E T N N 5 5aA4f2i a1f w 2 5is R
U T
A E
F w Y o R
- L E T - - T r E e - A e F n r e W t A o u ,
r a S i s oh u D W N t s wg s E h D O a e Tih s E rg E I u r Ht e F oi R T t P niw r tH E
E A A
c i s
wo P D a-N L t L N rh O n wet - e A eg I
G S
I i c eh mg onnw li eo i n
P ni eH N T t ni FLdL L I G -
E I E l a iH i - R -
N U
N I
a u
mc oi a-th mmc-aang m
a TN O
ml ae L n t g ng eeiv e EI ev L a uo oi t t oa t NT t e A M M AL CH SSCT S I A SL N A BL O E RO I T . . . . .
US .
T S a b c d e TI a C
N U . .
F 4 5 l_
m>y m7CZ y u (^ yw" $ QoZMZe ZO-
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
'n
$ EUUcTIcNAL UNIT TRIP SETPOIrc ALLOWABLE VALUES in 7 6. AUXILIARY FEEDWATER C
2 y a. Automatic Actuation N.A. N.A.
Logic
- b. Steam Generator Water 2 25% of narrow range 2 23.3% of narrow range l Level--Low-Low instrument span each instrument span each steam steam generator generator C. Undervoltage - RCP 2 2680 volts 2 2640 volts l
1
Pumps l
- 7. LOSS OF POWER w
l S a. 4.16 kv Emergency Bus 2 3255 volts bus 2 3222 volts bus voltage w Undervoltage (Loss of voltage
- 5 3418 volts bus voltage
- th Voltage) co
- b. 4.16 kv Emergency Bus 2 3675 volts bus 2 3638 volts bus voltage Undervoltage (Degraded voltage" 5 3749 volts bus voltage Voltage)
- 8. ENGINEERED SAF't? FEATURE ACTUATION SYST~i INTERLOCKS 1
$ a. Pressurize .-russure, P-ll 5 2000 psig 5 2010 psig '
tn Z
g b. Low-Low T avg' E-12 g (Increasing) 544 F 5 547 F Q (Decreasing) 543 F 2 540 F
=
,0 c. Steam Generator Level, P-14 (See 5. above)
- d. Reactor Trip, P-4 N.A. N.A.
- Refer to appropriate relay setting sheet Calibration requirements.
l.
mRl OC mam n
I TABLE 2.2-1 (Continued) b REACTOR TRIP SYSTEll INSTRUMENTATION TRIP SETPOINTS
' FUNCTIONAL UNIT TRIP SETPOINT LLOWABLE VALUES E 23syg Z
- 13. Steam Generator Water Level--Low - Low ' k of narrow range instrument an - each steam generator 2 $ narrow range instrument l m span - each steam generator
- 14. Deleted l
l
- 15. Undervoltage - Reactor 2 26F0 volts - each bus Coolant Pumps 2 2640 volts - each bus
- 16. Underfrequency - Reactor 2 57.0 Hz - each bus Coolant Pumps 2 56.9 HZ - each bus
- 17. Turbine Trip A. Low Auto Stop a 45 psig m Pressure 2 43 psig i B. Turbine Stop Valve Not Applicable o, Closure Not Applicable
- 18. Safety injection input Not Applicable Not Applicable from ESF
- 19. Reactor Coolant Pump Not Applicable Breaker Position Trip Not Applicable 5
2 2
2 5
f
y TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMEhTATION TRIP SETPOINTS I
g FUNCTIONAL UNIT TRIP SETPOINT ALLOVABLE VALUES
- 4. STEAM LINE ISOLATION w
- a. Manual Not Applicable Not Applicable
- b. Automatic Actuation Not Applicable Not Applicable Logic
- c. Containment Pressure-- f 16.2 psig f 17.5 psig l High-High
- d. Steam Flow in Two Steam f A function defined as follows: $ A function defined as follows:
w Lines--High, Coincident A op corresponding to 40% of full A Ap corresponding to 44% of full S with T --Lov-Lov steam flow between 0% and 20% load steam flov between 0% and 20% load !
and then a op increasing linearly and then a op increasing linearly
" to a op corresponding to 110% of to a op corresponding to 111.5% of i
l $ full steam flow at full load with full steam flow at full load with~
T,,, 1 543'F T,,, 2 540'F l
- e. Steam Line Pressure--Lov 2 585 psig 1 575 psig
- 5. TURBINE TRIP AND FEED VATER ISOLATION 73,2f, M. 57,
- a. Steam Generator Vater 5 A f narrow range instrument f 7M / f narrow range instrument Level--High-High span each steam generator span each steam generator l
b e
e M
5
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATIAN SYSTEM INSTRUMENTATION TRIP SETPO A FUNCTIONAL UNIT r,; TRIP SETPOINT ALLOWABLE VALUES f 6. AUXILIARY FEEDWATER E a. Automatic Actuation Z N.A.
Logic N.A.
u 26Y. 3?*j
- b. Steam Generator Water a Level--Low-low ~f narrow range instrument span each steam generator f narrow range instrument l l span ach steam generator
- c. Undervoltage - RCP h 2680 volts 2 2640 volts
- d. S. I.
See 1 above (all SI setpoints)
- e. Trip of Main feedwater N.A.
Pumps N.A.
- 7. LOSS OF POWER
- a. 4.16 kv Emergency Bus
- 2 3255 volts bus voltage
- 2 3222 volts bus voltage
- Undervoltage (Loss of Voltage) o$ s 3418 volts bus voltage *
- b. 4.16 kv Emergency Bus 2 3675 volts bus voltage
- Undervoltage (Degraded Voltage) 2 3638 volts bus voltage
- s 3749 volts bus voltage *
- 8. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INTERLOCKS
- a. Pressurizer Pressure, s 2000 psig P-ll s O')l0 psig 3E b. Low-Low T S? (Increasi$), P-12 544*F
$ (Decreasing) 543*F s 547*F 2 540*F 5 c.
2 Steam Generator Level, P P-14 (See 5. Above)
. d. Reactor Trip, P-4 N.A.
E N.A.
- Refer to appropriate relay setting sheet calibration requirements.
ATTACllMENT II Westinghouse letter CAW-94-600, dated March 17,1994," Application For Withholding Proprietary Information From Public Disclosure," with the following enclosures: Affidavit, Proprietary Information Notice, and Copyright Notice.
WCAP-13992, Proprietary Class 2," Steam Generator Lower Level Tap Relocation Assessment For J. M. Farley Nuclear Plant Units 1 and 2."
WCAP-13993, Proprietary Class 3, " Steam Generator I;)wer Level Tap Relocation Assessment For J. M. Farley Nuclear Plant Units I and 2."
l Y
w-----.------.. _ _ _ _ _ _ _ _ . _ . _ _ . _ _ . - - _ . _ _