ML20127P745
| ML20127P745 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/25/1993 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20127P723 | List: |
| References | |
| NUDOCS 9302020064 | |
| Download: ML20127P745 (86) | |
Text
{{#Wiki_filter:. _ _ - _ _ _ - _ _ _ _ I ATTACllMENT 4 PROPOSED TECIINICAL SPECIFICATION AMENDMENTS FOR CATAWBA D64 930125 gj0gOCK05000433
< P PDR
L 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2. APPLICABILITY: As shown in Table 3.3-1. ACfl0N: I As shown in Table 3.3-1. SURVEILLANCE REQUIREMENTS . I 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated.0PERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1, 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least onct per 11 months.-*~ l Each test shall include at least one train such that bot: trains are tested at least once per 36 months and one channel per f uncth.1 such that all channels are tested at least once every.N times 18 months where N is the total numter of redundant channels in a specific reactor trip function as shown in the
" Total No. of Chtnnels" column of Table 3.3-1. The response time of 4TOs associated with the Reactor Trip System shall be demonstrated to be within their limits at least once per 18 months. i
~ _ _
nerformed
*This surveillance need--n@ hand-e-ffE"fa.f.tr+H e time testing portion of Aitem 1-2 for Unit 2 until prior to M 5Tlowing the Unit 2 first refueling.
CATAWBA - UNITS 1 & 2 3/4 3-1 Amendment No. (Unit 1) Amendment No. 1 (Unit 2)
~
s TABLE 3.3-1 FOR UNIT 1 g 9
$ REACTOR TRIP SYSTEM INSTRUMENTATION 5
# MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE OPERABLE MCOES ACTION j OF CHANNELS TO TRIP E FUNCTIONAL UNIT u
" 2 1 2 1 2 1
- 1. Manual Reactor Trip 2 3 A , 4*, 5* 10 2 1 y
- 2. Power Range, Neutron Flux 3 1, 2 2 4 2
- a. High Setpoint 2 3 11##, 2 2 4
- b. Low Setpoint 4 2 3 1, 2 2
- 3. Power Range, Neutron Flux <;
Hi'h g Positive Rate > 2 1 2 Iff#, 2 3 [ w 4. Intermediate Range, Neutron Flux k - .
> 5. Source Range, Neutron Flux 2 2## 4 2 1 w a. Startup 1 2 3*, 4*, 5* 10 A b. Shutdown 2
- 6. Overtemperature AT 3 1, 2 6 Four Loop Operation 4 2
- 7. Overpower AT 3 1. 2 6 l Four Loop Operation 4 2
((
=a 1 6*
g 4 2 3
- 8. Pressurizer Pressure-Low j $[
EE FF L1 ee s. i 1 4
n M TABLE 3.3-1 (Continued) UNIT 1 J'
> REACTOR TRIP SYSTEM INSTRUMENTATION 6
7 MINIMUM c TOTAL NO. CHANNELS CHANNELS APPLICABLE 5 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION C . y 9. Pressurizer Pressure-High 4 2 3 1, 2 o~ l C
- 10. Pressurizer Water Level-High 3 2 2 1 6
- 11. Reactor Coolant Flow-Low
. a. Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1 6 any oper-ating loop each oper-ating loop
)
y
- b. Two Loops (Above P-7 and 3/ loop 2/ loop in two oper-2/ loop each oper-1 6 ( '
below P-8)
- ating loops ating loop .
y 12. Steam Generator Water 4/stm 2/sta gen 3/sta gen 1, 2 6* I w Level--Low-Low gen in any each operating operating sta gen sta gen
- 13. Undervoltage-Reactor Coolant 4-1/ bus 2 3 1 6 Pumps (Above P-7)
FF ( [ [ 14. Underfrequency-Reactor Coolant 4-1/ bus 2 3 1 6 E gg Pumps (Above P-7)
- 15. Turbine Trip-
. EI
- a. Stop Valve EH Pressure 4 2 3 INN 6 (
- b. hurbneStopValveClosure 4 4 1 IfM# 11 EE ,f gg 16. Safety Injection Input ee from ESF 2 1 2 - 1, 2 3 7 l J Sc we r v
n m TABLE 3.3-1 (Continued) UNIT 1
) -
g REACTOR TRIP SYSTEM INSTRUMENTATION 5
, MINIMUM c TOTAL NO. CHANNELS CHANNELS APPLICABLE 5 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTICN
.-e
[ ' 17. Reactor Trip System Interlocks g a. Intermediate Range
<(-
Neutron Flux, P-6 2 1 2 2M 8
- b. Low Power Reactor Trips Block, P-7 P-10 Input 4 2 3 1 8 or P-13 Input 2 1 2 1 8 g c. Power Range Neutron
- Flux, P-8 4 2 3 1 8 y d. Power Range Neutron 4 2 3 1 8
+ Flux, P-9
- e. Power Range Neutron Flux, P-10 4 2 3 1 8
- f. Power Range Neutron
(( Flux, Not P-10 4 3 4 1, 2 8 on l
@@ g. Turbine Impulse Chamber %[ Pressure,'P-13 2 1 2. 1 '8 E E 18. Reactor Trip Breakers '~ 2 1 2 1, 2 9, 12 ;
2 1 2 3*, 4*, 5* 10
- 19. Automatic Trip and Interlock '
((. . Logic 2 2 1 1 2 2 1 2 3 I, 4* , 5*
"/
10
- -l I
n g 20. Reactor Trip Bypass Breakers N.A. N.A. N.A. 1,2,3*,4*,5* 13
.M.
TABLE 3.3 1 (Continued) UNIT 1 j ' TABLE NOTATIONS ' l
*0nly if the Reactor Tiip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.
**Cc; ply with th: provision; cf Specification 3.3.0, for any p;rtica of-the
-ehenn:1 r;quir:d t; b; OPERA 0L: by Specif4cetici, 0.3.2--
##Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
###Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
####Above the P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours. ACTION 2 - With'the number of OPERABLE channels one less than the Total
.STARTUP and/or POWER OPERATION may proceed Number provided oftheChannels,ing follow conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 6 hours,
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification 4.3.1.1, and
- c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per Specification 4.2.4.2.
ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
- a. Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or -
- b. Above the P-6 (Intermediate Range Neutron Flux Interlock)
St+ point but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above ITG of RATED THERMAL POWER. CATAWBA - UNITS 1 & 2 3/4 A 3-5 Amendment No. (Unit 1)1 j Amendment No. (Unit 2)
0 v. TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continued) . ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving i positive reactivity changes. ACTION 5 - Delete l l ACTION 6 - With the number of OPERABLE channels one less than the Total l Humber of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 6 hours, and
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification 4.3.1.1.
ACTION 7 =0:1cte= WSC/CT A ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour determine by observation of the associated permis'sive status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3. ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE. ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or open the Reactor trip - breakers within the next hour. ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours. ACTION 12 - With one of the diverse trip features (Undervoltage or shunt trip attachment's inopera'ble, restore it to OPERABLE status within 48 hours or declare the breaker inoperable and apply ACTION 9. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for perform-ing maintenance to restore the breaker to OPERABLE status. With the breaker bypassed, apply ACTION 9. ACTION 13 - With any reactor trip bypass breaker inoperable, restore the bypass breaker to OPERABLE status prior to placing it in service. CATAWBA - UNITS 1 & 2. 3/4 A 3-6 Amendment No.1 (Unit 1) Amendment No. (Unit 2)
Iwrar A +s e rap.s 3 HA : - 4 ad 3/+ f., s -6 W T s k -r L t. nv 4 & Orne+ arc c knne.lt s n e. len %an -the l g reJ%rc rhu
/ win.kv% chan ne/r offrMdur gud
~
< nap.rostu cAn n ad +o orenAct.v s +n-tvr w'ds~ L k ovre or bu is at -
leart Hor s r w 0 6'l w s d. , ~+4 e- ne++ 6 A ave.r,. , k savtr, onc. channe) owl I,c 4 yta n c E for w%4 h ovct . ' for survis(lanw fe.rn'n3 per. Ey ed,-{,La$o~ '+ 3. I,I, prohlc0 , . fL.e. s14cr c kasnel 'L oPss?AdLB". o i
-g TABLE 3.3-2 FOR UNIT 1 5 REACTOR TRIP SYSTEN INSTRUMENTATION RESPONSE TIFFS c:-
5
- r-h FUNCTIONAL UNIT' RESPONSE TIME'
. z 3 - 1. Manual'IIeactor Trip N.A. g 2.- Power Range, Neutron Flux i 0.5 second*
- 3. P w r Rang , Neutron Flux, High Positwe ' date .. N.A.
- 4. Intermediate Range, Neutron Flux N.A. .
-5. Source Range,-Neutron Flux N.A.
.g
'6. Overtemperature AT $ 8 seconds *
> 7. Overpower AT $ 3 seconds *
- 8. Pressurizer Pressure-Low _ 1 2 seconds
- 9. Pressurizer Pressure-Hf gh 1 2 seconds
! 10. Pressurizer Water Level-High M.A. J gg. g g ..
.a2 52-
'aa. .i.
.P P
- Neutron detectors are exempt from response. time testing. . Response time.of the neutron flux signal portion _
g m-of. the channel shall be measured from detector output or input of first electronic' component in channel. eQ4 A
.C C
- n Tt as.
)wy.
nn
=e t
2 ( 4
-,- y , we - , ,r..-c m .e. . . .__m_ m_._ _ _____.___ _ _ _ _ _ -..._mm._ _ _ _ _ _. _. ._..m.__ .___ . - _ . . _ ._m._.. _ ___. __,__. _ . _ . _ _ _ _ .
- v 'h n TABLE 3.3-2 FOR UNIT 1 (Continued) l ., n g-: REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES
- 2. -
e c- FUNCTIONAL UNIT- RESPONSE TIME d 11.- Low Reactor Coolant Flow
-b a. Single' Loop.(Above P-8) $ 1 second
- b. - Two Loops (Above P-7 and below P-8) $ 1 second
- 12. Steam Generator Water Level-Low-Low
- a. Unit 1 < 3.5 seconds
- b. Unit 2- 32.0 seconds
- 13. Undervoltage-Reactor Coolant Pumps 5 1.5 seconds l R
* ' 14.
Underfrequency-Reactor Coolant Pumps -< 0.6 second 4 !- Y 15. Turbine Trip !' . m-
. a. Stop Valve EH Pressure-Low N.A.
- b. Turbine Stop Valve Closure M.A.
.l
- 16. Safety Injection Input from ESF N.A.-
I 2 h 17. 2o. Reactor Trip System Interlocks N.A. N
- aa
- 18. . Reactor Trip Breakers M. A.
. lh
-i c; E .
22- ' 19. Automatic Trip and Interlock Logic N.A. IL P P '9$ es-
, vi .
.I' 9 th .
- R 22 s.
. . +o -
F K e' ' e.-w e-- y e s
-e -
+Py ye y- + , , w ~ vy%-- a, w -y-a +- - ,,e -- w n ,p w er we i w - w-'e 4 . _ _ _ _ m
;n TABLE _4 3-1 FOR UNIT 1 ,
f% REACTOR TRIP SYSTEM INSTRtTAENTATION SURVEILLANCE REQUIREMENTS
~
TRIP c- ' ANALOG ACTUATING M00ES FOR
$ CHANNEL DEVICE WICH g CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE
' J FUNCTIONAL UNIT- CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
-g
- 1. Manual Reactor Trip N.A. N.A. N.A. R(14) N.A. 1, 2, 3* , 4* , 5*
- 2. Power Range, Neutron Flux
- a. High Setpoint 5 D(2,4), -M- R N.A. N.A. 1, 2 M(3,4), 'l Q(4,6),
R(4..5)
- b. Low Setpoint 5 R(4) 4t-sft/b) N.A. N.A. IN#, 2 g
- 3. Power Range, Neutron Flux, High Positive' Rate M.A. R(4) -M-( N.A. N.A. 1, 2 l
u
- . E 4. Intermediate Range, S R(4,5) S/U(1),4- N.A. N.A. 1#N, 2 - l Neutron Flux
~
?
A <, 5.- Source Range, Neutron Flux 5 R(4,5) S/U(1);M(9) N.A. N.A. 2 M ,.3, 4, 5 l } [ -
.6. Overtemperature AT- S R -*- ( N.A. N.A. 1, ' 2 l l kk 7. Overpower AT S R -M-_( N.A. N.A. 1, 2 l 22 gg 8.. Pressurizer Pressure-Low S. R -M- R N.A. N.A. 1 -l
.IE 9.' Pressurizer Pressure-!!igh 5 _ R' -M- Q N.A. N.A. 1, 2 l
~
- 10. ' Pressurizer Water Level-High 5 .R -M- Q N.A. N.A. 1 'l
~ 11. Reactor Coolant F1ow-Low S :
R +Q M.A. N. A. 1 -l
==
i 4 - g upapa -r. --,yi. We 4 '*M*1p' p'1' P 'W v F" 'N -' ^ - - " - - - - - - - - - - - " - - - - ~ ' - - - ~ - ' " - - - - - - - - - - " - - - - - - " ^ ' - - - ^ - ' ' '
n TA8LE 4.3-1 FOR UNIT 1 (Continued) -
~
D
'E REACTOR TRIP SYSTEM INSTRLMENTATION SURVEILLANCE REQUIRENENTS
, TRIP j c.- ANALOG ACTUATING N00ES FOR
! $ CHANNEL DEVICE idHICH g CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED C .
- 12. Steam Generator idater Level- -ft-Q Low-Low S R(13), N.A. N.A. 1, 2 M. '
13.. Undervoltage - Reactor Coolant N.A. R N.A. -4 Q N.A. 1 Pumps l
- 14. Underfrequency - Reactor N.A. R N.A. 4t-Q N.A. 1 w Coolant Pumps l (.
D.
> '15. Turbine Trip .
-l w a. .Stop. Valve EH Pressure M.A. R N.A. S/U(1, 10) N.A. 1#
,', - Low
. b. Turbine Stop Valve Closure M.A. R N.A. S/U(1, 10) N.A. If l l 16. Safety Injection Input from N.A. N.A. .N.A. R**~ N.A. 1, 2 i ESF l yg
- 17. Reactor Trip System Interlocks .
=g
- a. . Intermediate Range
! kg : Neutron Flux, P-6 N.A. R(4) -M- R N.A. N.A. 2ff 55 m yy Ei,[Uih[bi "t ") M") "^ ""
. 1 I 'b b.-e Power' Range Neutron . .
( Flux,-P-8
- gg
.M.A. . R(4) -M(6)-& N.A. N. A. - 1 C.-dr. Low Power Range Neutron -
j
- ,
- L:1 Flux, P-9 N.A. R(4) --M(6}- & . M.A. N.A. 1-L . c+ o I
mp h.
** This surveillance need no '
s UP following the Unit l'first ! refueli . l Nb-l- t (T i. 2_ . . - - . .. , . ... m-.. _ . . . . -
, . _ . . . _ . . __.___.m, _ . ~ - _ _ . - . . , .
n TABLE 4.3-1 FOR UNIT 1 (Continued) -T. Z
.g .
-{
REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIRENENTS
, TRIP c ANALOG ACTUATING N00ES FOR 5 -
CHAleIEL OEVICE WHICH ~ M - CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION TAIRVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED E, -
- 17. Reactor Trip System Interlocks (Continued) t>
M. Power Range Neutron Flux P-10 N.A. R(4) 4*ffe-k M.A. M.A. I e., 4 Power Range Neutron M.A. R(4) ^ -M(e)-R N.A. N.A. 1, 2 w a' k - '
> .C _.g ' Turbine Impulse Chamber' w Pressure, P-13 N.A. R -M(4)-d N.A. M.A. 1 ~ 18. Reactor Trip Breaker N.A. M.A. N.A. N(7. 11) N.A. 1, 2, 3*, 4*, 5*
- 19. Automatic Trip and Interlock N.A. - N. A. N.A. M.A. M(7) 1, 2, 3* , 4 * , 5*
Logic
- 20. , Reactor Trip' Bypass M.A. M.A.- N.A. M(7,15)R(16) M.A 1, 2, 3*, 4*, 5*
Breakers k.k . en w ?; 50-
.4
a f l TABLE 4.3-1 FOR UNIT 1 (Continued) {* TABLE NOTATIONS'
- Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.
# Above P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.
## Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
### Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint. ;
(1) If not performed in previous tIays7 3 l l f (2) Comparison of calorimetric to excore power indication above 15% of RATED - l THERMAL POWER. Adjust excore channel gains consistant with calorimetric ! power if absolute difference is greater than 2%. The provisions of - Specification 4.0.4 are not applicabic for entry into MODE 2 or 1. (3) Single point comparison of incere to excore axial flux difference above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. The' provisions of Specification 4.0.4 are not aoplicable for entry into MODE 2 or 1. ; (4) Neutron detectors may be excluded from CHANNEL CALIBRATION. , (5) Detector plateau curves shall be ootainad, evaluated and compared to manufacturer's data. For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1. (6) Incore - Excore Calibration,.above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE.2 or 1. (7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
.(8) Vittrpownstrater than or equal to the interlock setpoEihe-requiref ANALOG CHANNEL OPERATIONAL-TESLshall contist-of-veFTTy~ing that the Qd~'g interlock is in the required-state by ollTrving-the-strmissive status light. -
~
(9) " =thly surveillance in MODES 3*, 4*, and Sa shall also include verifi-gAch/, cation that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive status light. (10) Setpoint verification is not applicable. (11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shell include independent verifi-cation of the operability of the Undervoltage and Shunt trips. (12) Deleted (13) For Unit 1, CHANNEL CALIBRATION shall ensure that the filter time constant associated with Steam Generator Water level Low-Low is adjusted to a value less than or equal to 1.5 seconds. (14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERASILITY of the Bypass Breaker trip circuit (s). CATAWBA - UNITS 1 & 2 3/4 A 3-12 Amendment No.1 (Unit 1) { Amendment No. }(Unit 2)
4,O CV{ht%CS t TABLE 4.3-1 FOR UNIT 1 (Continued) ' TIU S IS46- . . _ _ w
' TA8LE NOTATIONS ,
(15) A local. manual' shunt _ trip on the bypass breakers shall be performed prior-- to' placing breaker in service. j (10) The automatic undervoltage trip capability shall-be. verified OPERABLE,- ' I s P h
'i r
t f i T
'I j
~
J r i
?
1 h
- CATAWBA-[ UNITS.1&2 - 3/4 A 3-12a Amendme'nt No.101 (Unit _-1) ' ~l:
Amendment No.- 95 (Unit 2)
"u y r , +cm Nie- mown e - n* s-s- new -m.~e= ns -s.e -,N.-+ - =-e- -
.N e'~N--- ~ N -r
I O TABLE 3.3-1 FOR UNIT 2 { i , h REACTOR TRIP SYSTEM INSTRUNENTATION MININUM z TOTAE NO. CHANNELS CHANNELS APPLICABLE
. d FUNCTIONAL UNIT - 0F CHAMIELS TO TRIP OPERABLE MODES ACTION
. k 1. Manual Reactor Trip 2 1 2 1, 2 - 1
- 2 1 2 3*, 4*, 5* 10
- 2. Power Range, Neutron Flux
- a. Higie Setpoint 4 2 3 1, 2 2
- b. Low Setpoir.t 4 2 3 1M,2 2
- 3. Power Range, Neutron Flux 4 2 3 1, 2 2 High Positive Rate ,.
R
- 4. Power Range, Neutron Flux, 4 2 3 1, 2 2
<= High Negative Rate
- 5. Intermediate Range, Neutron Flux 2 1 2 IM,2 3
- 6. Source Range, Neutron Flux
- a. .Startup 2 1 2 2M 4
- b. Shutdown 2 1- 2 3*, 4 * , S* 10
{ { . 7. Overtemperature AT sa Four Loop Operation 4. 2 3 1, 2 6 II
== 8. Overpower AT
(( Four Loop Operation 4 2 3 1, 2. 6 oo
~
- 9. Pressurizer Pressure-Low 4 2 3 1 E**-
== -
t' 33
- up vu - '
. - ~ + , e , m w ,.- , - - _ _ . _ _
1 k> TABLE 3.3-1 FOR UNIT 2 (Continued) - f b MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE l FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE ~ MODES ACTION x. 3 10. Pressurizer Pressure-High 4 2 3 1, 2 6* l N 11. Pressurizer Water Level-High 3 2 2 1 6
~~
- 12. Reactor Coolant Flow-Low
- a. Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in -1 6 any oper- each oper-ating loop ating loop
- b. Two Loops-(Above P-7 and 3/ loop 2/ loop in 2/ loop 1 6 '
below P-8) two oper- each oper-R ating loops ating loop
<= 13. Steam' Generator Water 4/sta 2/sta gen in any 3/sta gen 1, 2 6**-' l'.
y Level-Low-Low gen each w operating operating sta gen sta gen
- 14. Undervoltage-Reactor Coclant 4-1/ bus 2- 3 1 6 Pumps (Above P-7)-
(( 15. Underfrequency-Reactor Coolant 4-1/ bus 2 3 1 6 ss Pumps (Above P-7) tt
==. 16. Tuitine' Trip ,, a. Stop Valve EH Pressure 4- 2 3 INN 6 ,o ,o - Low s b. Turbine Stop Valve Closure 4 4 1 INN 11 i .
g g 17. Safety Injection Input -
= s., from ESF 2 1- 2 1, 2 7 nn l vA4
_2
. c n TABLE 3.3-1 FOR UNIT 2 (Continued) ,
j;[ 3 i HINIMUM h TOTAL NO. CHANNELS CHAa.#iELS - APPLICABLE TO TRIP OPERABLE MODES ACTION , FLHCTIONAL UNIT OF CHANNELS h 18. Reactor Trip systcar Interlocks
- a. Intermedataf$ange 28f 8
~
g 2 1 2 R Neutron Flasci F-6
- b. Low Power Reactor Trips Block, P-7 3 1 8 P-10 Input 4 2 or 8 P-13 Input 2 1 2 1
^
- c. Power Ringe Neutron 1 8 4 2 3 1:
8 Flux, P-8 s 8 4 2 3 1
= d. Power Range Neutron y Flux, P-9
- e. Power Range Neutron 1 8
-4 2 3 l Flux, P-10
- f. Power Range Neutron 1, 2 8 4 3 4 Flux, Not P-10 Turbine Impulse Chamber kk gg g.
Pressure, P-13 2 1 2 1 8 55 19. Reactor Trip Breakers 2 1 2 1, 2 9, 12 22 2 1 2 3*, 4*, 5* 10
.o .o
- 20. Automatic Trip and Interlock 2 1 2 1, 2 3*, 4*, 5*
07 10 2 1 2 gg Logic oo 1, 2, 3*, 4*, 5* 13
$ $ 21. Reactor Trip Bypass Breakers N.A. N.A. N.A.
30 v4
.' i TA8tf 3.3-1 70R UNIT 2 (Continued)
{ TABLE NOTATIONS
*0nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.
-!th th pr "!!!::: Of th:
**--oanne::;1y! regird te he OPSAASLE 4 !;::f f f::ti:n 3,3rer-Of !;;;fft::tt:0 3.3.2, f r Ors p;rti
##Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
###8elow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint. <
####Above the P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint. l kCTIONSTATEMENTS ACTION 1 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERA 8LE status within 48 hours or be in at least HOT STAN08Y within the next 6 hours.
ACTION 2.- With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: 4
- a. The inoperable channel is placed in the tripped condition within 6 hours, i
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours.
for surveillance testing of other channels per-Specification 4.3.1.1, and-
- c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL F0WER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per
. 12 hours per Specification 4.2.4.2. :
ACTION 3 - With the number of channels OPERABLE one less than the Minimus Channels OPERABLE requirement and with the THERMAL PCWER level: '
- a. Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERA 8LE status prior to. increasing THERMAL POWER above the P-6 Setpoint; or. ,
- b. Above the P-6 (Intermediate Range Neutron Flux Interlock).
Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior te increasing THERMAL POWER above 10% of RATED THERMAL POWER. CATAWBA - UNITS 1 & 2 3/4 8 3-5 Amendment No. 1 (Unit 1) f) ' Amendment No. (Unit 2). e n- wr,-,'< r --_m e- --_.2 _m , am,_.m _ _ . - _ . _ ____-_.__---____.m - - ,-- .- .- ..,m m, , - _ . . - . , ~ . - - -,,w.-. --e
.p m r . ap. a+ .
- .. ;< yey:,p w ,. .
,n . .,
TABLE 3.3-1 FOR UNIT 2 (Continued) { ACTION STATEMENTS (Continued) m ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes. ACTION 5 - Delete ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in th'a tripped condition within 6 hours, and
- b. The Minimum Channels OPERABLE requirement is met; however. -
the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification 4.3.1.1. ACTION 7 Gelett- lI/SCRT A ACTION 8 - With less than the Minimus Number of Channels OPERABLE, within . I hour determine by observation of the associated permissive m status light (s) that the interlock is in its required state h for the existing plant condition, or apply Specification 3.0.3.i ACTION 9 - With the number of OPERABLE channals one less than the Minimum Channels OPERABLE requirement, be in at least HOT STAND 8Y within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1, provided the other channel fi, OPERABLE. ACTION 10 - With the number of OPERABLE channels one less than the Minieum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or open the Reactor trip breakers within the next hour. ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable
' channels are placed in the tripped condition within 6 hours.
ACTION 12 ,.With one of the diverse trip features (Undervoltage or shunt
$ trip attachment) inoperable, restore it to OPERABLE status within
- 48. hours-or declare the breaker inoperable and apply ACTION 9.
(iThe breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for perform-ing maintenance to restore the breaker to OPERABLE status. With the breaker bypassed, apply ACTION 9. ACTION 13 - With any reactor trip bypass breaker inoperable, restore the bypass breaker to OPERABLE status prior to placing it in service. CATAWBA - UNITS 1 & 2 3/4 8 3-6 Amendment No. 1 Amendment No. (Unit 1) (Unit 2) f
n TABLE 3.3-2 FOR UNIT 2 I.
- . REACTOR TRIP SYSTEM INSTRUNENTATION RESPONSE TIMES c .
i'i FUNCTIONAL UNIT RESPONSE TIME l' C , 1. Manual Reactor Trip N.A. l 'C 2.' Power Range, Meutron Flux 1 0.5 second* F
- 3. Power Range, heutron Flux, -
High Positive Rate N.A.
- 4. Power Range, Neutron Flux, High Negative Rate .
1 0.5 second* ,.. y 5. Intermediate Range, Neutron Flux N.A.
'"" 6. : Source Range, Neutron Flux N.A.
Y
" 7. Overtemperature AT i 8 seconds" -l
!- 8. Overpower AT , 1 8 seconds
- l f 9. Pressurizer Pressure-Low .i 2 seconds FF 3 10.- Press rizer Press re-ni.h -< 2 seconds s=
,; o 3k 11. Pressurizer Water Level-High N.A..
"O' i as tgg s
,r,r -
Ap4 39 22
. oa i _ ; ; ?* Neutron detectors are exempt from response. time testing. Response time of the neutron flux signal portion of the channel shall be measured free detector ~ output' or input of first electronir component in channel.
1 4 e m - + - ,.4, ,- - .
n e h n TABLE 3.3-2 FOR UNIT 2 (Continued) 51 g
> i REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES h L:3 I
, if
>.,4 RESPONSE TIME r 5 FUNCTIONAL UNIT %g.
g;,, 5 g . 2p% :+A y
- 12. Low Reactor,Caeleaf Flow -
g@ u = y, g < 1 second 4
- a. Single Loop (Above P-8)
- b. Two Loops'(Above P-7 and below P-8) 5 I second ,,, ;l} l
.g w
- 13. Steam Generator Water Level-Low-Low g
< 3.5 seconds d$
- a. ' Unit'1 -
^2 Un,it ,2 -7 2.0 seconds q b.
4:. g 14. Undervoltage-Reactor Coolant Pumps i 1.5 seconds .a ca 15. Underfrequency-R'eactor Coolant Pumps 5 0.6 second ~p[ u .
# _?
E 16. Turbine Trip ll5 Stop Valve EH Pressure-Low M. A. ; 'r a.
- b. Turbine Stop Valve Closure N.A. .
N.A. 5.
- 17. Safety Injection Input from ESF '2 kk
= = JB. . Reactor Trip System Interlocks N.A. -3 %
=e o.
gg .
- 19. Reactor Trip Breakers N.A. "O 2 s.
h . u... a. c a ~ f f 20. Automatic Trip and Interlock Logic M.A. l @a dg Ljs
' q f) " =g .
gg vo w . WJ . aff VV 7
.4
- v. .
.7
.7 t
^
r> 4 , fi2- TABLE 4.3-1 FOR UNIT 2 q h REACTOR TRIP SYSTEN INSTRUMENTATION SURVEILLANCE REQUIREMENTS c TRIP 5 ANALOG ACTUATING MODES FOR d- - CHANNEL DEVICE WHICH
~ CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE C FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST 15 REQUIRED
- 1. Manual Reactor Trip N.A. N.A. N.A. R(14) N.A. 1, 2, 3*, 4*, S*'
- 2. Power Range, Neutron Flux
- a. High Setpoint S D(2, 4), -ft- GL N.A. N.A. 1, 2 l e4(3, 4),
Q(1, 6), R(4, 5) e R, s
- b. Low Setpoint S R(4) +t-Sfutl) N.A. N.A. 1###, 2 l
- Power Range, Neutron Flux, N.A. N.A.
- 3. M.A. R(4) 46-E 1, 2 [
';' High Positive Rate e
- 4. Power Range, Neutron Flux, M.A. R(4) Q N.A. N.A. 1, 2 l
High Negative Rate -
- 5. Intermediate Range, S R(4,5) S/U(1),46- N.A. N.A. 199f, 2 g Neutron Flux R
- 6. Scurce Range, Neutron Flux 5 -R(4. 5) S/U(1);M(9) N.A. N.A. 2##, 3, 4, 5 g a% 7. Overtemperature AT S' R -M- ( N.A. N.A. 1, 2 l zz
.?? 8. Overpower AT S R 4t- Q N. A. N.A. 1, 2 l
- 9. Pressurizer Pressure-Low 5 R NR N.A. N.A. 1 l
> T[E
"" 10. Pressurizer Pressure-fligh 5 R 46- A H. A. N.A. 1, 2 i OC 11. Pressurizer Water Level-High 5 R -it- Q N.A. N.A. I g
- 12. Reactor Coolant Flow-Low S R -M-Q N.A. N.A. 1 l
g
) -
?
- 4
-c m TABLE 4.3-1 FOR UNIT 2 (Continued) ag k> ~r 1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVE!LLANCE REQUIREMENTS ,
h ; m TRIP A c ANALOG ACTUATING K) DES FOR H 5 CHANNEL DEVICE . a -_ Wi!CH -y g .w - CHANNEL OPERATIONAL OPERATIONAL ACTUATION " ?- SURVEILLAIEE J~ '5
; CHANNEL y " CALIBRATION TEST TEST LOGIC TEST ~ IS REQUIRER" g FUNCTIONAL UNIT CHECK _
' 2 N.A. H.A. 1, 2
- 13. Steam Generator Water Level- S R(13) -M- Q Low-Low N.A. -M- R N.A. 1 l
- 14. Undervoltage - Reac*er Coolant N.A. R Pumps is'5 N.A. 1 ;
y
- 15. Underfrequency - Reactor N.A. R N.A. -M- ( %l7
} Coolant Pumps .
- 16. Turbine Trip S/U(1, 10) N. A. If
- a. Stop Valve EH Pressure M.A. R N.A. ~
o - Low ne N.A. S/U(1,10) N.A. If b
- b. Turbine Stop Valve Closure N.A. R
- 17. Safety Injection Input from ESF N.A. N.A. N.A. R**"- N.A. 1, 2 h .
- 18. Reactor Trip System Interlocks ,
j
- a. Intermediate Range i
(( am Neutron Flux, P-6 N.A. R(4) -M-R N. A. N.A. 2N. ._
,3 .
ee "8
*(') "(9) 1 b, -s,- Power Range Neutron N.A. 1 N.A. R(4) -M(4)-( N.A.
^^ Flux, P-8 I
EE c, & Low Power Range Neutron N.A. M.A. 1
-M(8)-(
37 Flux, P-9 N.A. R(4) 77 i t following the Unit I first
** This surveillance need not e pe .
- refueling. 1 a
.l k> Tt3tE 4.3-1 FOR UNIT 2 (Continued)
REACTOR TRIP SYSTEN INSTRLMENTAT'6fi SURVEILLANCE REQUIREMENTS c TRIP 5 ANALOG ACTUATING MODES FOR y CHANNEL DEVICE MtICH g CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE
-C FUNCTIONAL UNIT, CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
- 18. Reactor Trip System Interlocks (Continued)
- 0, -er . Power Range Neutron Flux, P-10 N.A. R(4) -M(63- R N.A. M.A. 1 e . 4, Power Range Neutron -
- i. m Flux, Not P-10
, 1 N.A. R(4) -M(9)- R N.A. N.A. 1, 2
=
w f. _g_ Turbine Impulse Chamber-4- y
.. Pressure, P-13 N.A. R ;;(G) R N.A. N.A. 1
- 19. Reactor Trip Breaker M.A. N.A. M.A. M(7, 11) N.A. 1, 2, 3*, 48, 58!
- 20. Automatic Trip and Interlock M.A. M.A. N.A. N.A. M(7) 1, 2, 3*, 4*. 5*
Logic
- l. kk21. Reactor Trip Bypass N.A. N.A. N.A M(7,15)R(16) N.A 1, 2. 3*. 4*, 5'
(( o 2 I 5.N i 22
==
l YA i 50 4 i ..
- - - - - ~. ,- ..
r
- Only if.~ ter Trip Systeie4rietiere: happen to be closed and the '
control we System is capable of rod withdrawal. >
# Abovei Trip:en Turbine Trip Interloc'k) 5etpoint.- " ,
. ~ :~ .. .
## Below P- termediate Range Neutron Flux Interlock)-Setpoint.
### Ra Neutron Flux Interlock) Setpoint.
Below P 10-(Lbw (1) If not performed in previous 7- Setpoint- .3lPowergdays l (2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is nreater than 25. The provisions of ; Specification 4.0.4'are not sont cable for entry into MODE 2 or 1. -3 (3) Single point compari',on of incore to exco,*g axial flux difference above-15% of RATED THERMAL. POWER. Recalibrate if the absolute difference is greater than or equal to .1%. The provisions of Specification 4.0.4 are . .: not applicable for entry into MODE 2 or 1. t (4) Neutron detectors may be excluded.from CHANNEL CALIBRATION. - -1 (5) Detector plateau curves shall be obtained, evaluated and compared.to I manufacturer's' data. For the Intermediate Range and Power Range Neutron-- l Flux channels the provisions of Specification 4,0.4 are not applicable for entry into MODE 2 or 1. gf ; (6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The $ provisions of Specification 4.0.4 are not applicable for entry into Y , MODE 2 or 1. ! (7) Each train shall be tested at least every 62 day. on a $TAGGERED TEST t BASIS. l (8) h er than or equal to the interlock setagiaLW: ? ANALOG CHANNEL 0 hall caa*4t ..^ verifying.that the g[ terlock is in the r ruissive status (9 .h tM y-surveillance in M00ES 3*, 4*, and 5* shall also include verifi ' thwe bety /) cation that pemissives P-6 and P-10 are in their required state' for l c existing plant conditions by observation of.the permissive status light.. , (10) Satpoint verification is not applicable, l (11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verifi-cation of the Undervoltage and Shunt. trips. ; (12) Deleted, i_; ; , (13) For Uni L CALIBRATION shall ensure that the filter time-constant associa Steam-Generator Water Level Low-Low is adjusted to a-value ; less than'or? equal,to 1.5 seconds. : (14) The TRIP ACTUATING DEVICE' OPERATIONAL TEST shall independently verify the I
~ OPERA 81LITY of the undervoltage and shunt trip circuits for the Manual 1 Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s). .
3/4 8 3-12 ;
- CATAWBA - UNITS 1 & 2 Amendment No.1 (Unit 1) y-i Amendment No. (Unit 2) ,
t A G .s_ _ . _ , _ _ _ _ _ __._l. ...#_ _ . _ , .f , .,,-.,.a..... R. ..,...,,a....,._,,o.,,. % ,L 3o ,
l TABLE 4.3-1 FOR UNIT 2 (Continued) Wb cHAtJWS i 7M$ ?AGC '! l TABLE NOTATION $- v _ . (15) A local manual shunt trip on the bypass breakers shall be perfonned prior to placing breaker in-service. l i (16) The automatic undervoltage trip capability shall be verified OPERABLE._ _ R I 1 1 l t 3 4
.i
+
33 . i i- CATAWBA - UNITS 1 & 2 -3/4.8 3-12a Aesndment No.101 (Unit 1) ] Amendment No. 95 (Unit 2).' . P f b i 5 w*r - + -
- h TF T "* b
m. _, ., A/D Cl(AA/(A3 INSTRUMENTATION D # 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTAT!ON _ , LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation j channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint-column of Table 3.3-4 and with RESPONSE TIMES as shown-in Table 3.3 5. APPLICABILITY: As shown in Table 3.3-3 1 ACTION:
- a. With an ESFAS Instrumentation or Interlock Trip Setpoint trip less ;
conservative than the value shown in the Trip Setpoint column but- 1 more conservative than the value shown in the Allowable Value column i of Table 3.3-4, adjust the Setpoint consistent with the Trip.Setpoint value,
- b. With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown:in the Allowable Values Column of Table 3.3-4 declare the channel inoperable and apply the applicable '
ACTION statement requirements of Table 3.3.3 until the channel is > restored to OPERABLE status with its Seipoint adjusted' consistent with the Trip Setpoint value.
- c. With an ESFAS instrumentation channel ~or interlock inoperable, take the ACTION shown in Table 3.3-3. i 3
k CATAWBA - UNITS 1 & 2 3/4 3-13 Amendment No.101 (Unit 1) Amendment _No. 95 (Unit 2)
=. - ,,
i
'!NSTRUMENTA?10N l
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the Engineered Safety Features Actuation System Inttrumentation Surveillance Requirements specified in Table 4.3'2. , , 4.3.2.2 The ENGIN5ERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.
- l i Each test shall include at least one train such that both trains are tested at l 1 east once per 36 months and one channel per function such that all channels !
are tested at least once per N times 18 months where N is the total number I of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3,3-3.
/
s surveillance need not, p2 vede n t inr4tems' Table 3.3-5 on Unit y2 upHerT6~ entering Hol snuiDCL'" f:lle"Q Unit h fvrTTng. CATAWBA - UNITS 1 & 2 3/4 3-14 Amendment No. (Unit 1) Amendment No. (Unit 2) g
a M e
..y TABLE 3.3-3 9 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5
MINIMUM E TOTAL NO. CHANNELS CHANNELS APPLICABLE Z
- O_f CHANNELS TO TRIP OPERABLE MODES ACTION FUNCTIONAL UNIT
~
** 1. Safety Injection (Reactor
" Trip, Phase "A" Isolation, feedwater Isolation,t..,ntrol-Room Area Ventilation Opera-tion, Auxiliary Feedwater-Motor-Driven Pump, Purge &
Exhaust Isolation, Annulus Ventilation Opeidtion, Auxiliary Building Filtered R Exhaust Operation, Emergency
- Diesel Generator Operation, T Component Cooling Water,
- 7. Turbine Trip, and Nuclear Service Water Operation)
- 2 1,2,3,4 18' 2 1
- a. Manual Initiation
*. 2- 1 -2 1,2,3,4 14
- b. Automatic Actuation .
Logic and Actuation y %- k>2 Relays 2;f 1, EE 22 c. Containment 3 2 2 1,2,3 15 l [C, 9 ~ 55 Pressure-liigh zz PP d. Pressurizer 4 2 3 1, 2, 3# 19 l96 Oi ew Pressure-Low . , ww 15
- e. Steam Line Pressure- 3/ steam line 2/ steam line 2/ steam line 1, 2, 3# l l 22 in any steam
! 3. 3. Low
"" line UU
l . TABLE 3.3-3 (Continued) ' ; ENGlHEERED SAFETY FEAIURES ACTUATION SYSTEM INSTRUMENIATION O
# MINIMUM 6:w: ::ts CilANNELS APPLICABLE 10TAL NO.
[ OF CilANNELS TO TRIP OPERABLE MODES ACTION w fuMCTIONAL UNIT
- 2. Containment Spray 1,2,3,4 18
)
m
- a. Manual Initiation 2 1 1
2 2 1,2,3,4 14
- b. Automatic Actuation 2 Logic and Actuation Relays 4 2 3 1,2,3 16 ,
- c. Containment Pressure- ~
liigh-liigh
" i. Containment Isolation a
w
- a. Phase "A" Isolation 2 1 2 1,2,3,4 18 h 1) Manual Initiation 2 1 2 1,2,3,4 14
- 2) Automatic Actuation o,
Logic and Actuation Relays Safety injection See item 1. above for all Safety Injection initiating ' tions and y< c, o
- 3) ,
requirements. g'Sy,
- b. Phase "B" Isolation (Nuclear Service Water Operat. ion) 1)- Manual Initiation 2 1 2 1,2,3,4 18 l $'i h
1 2 1, 2, 3, 4 14 Automatic Actuation 2 2) Logic and Actuation Relays - 4 2 3 1,2,3 16
- 3) Containment Pressure-liigfriligh i l
V
Y h w.
. J TABLE 3;3-3 (Continued)
S Y ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION N>
'E' . MINIMUM Z : TOTAL N0; CHANNELS CHANNELS APPLICABLE '
FUNCTIONAL UNIT OF CHANNELS- TO TRIP' OPERABLE MODES ACTION [ [ 3. Containment Isolation'(Continued) ,
- c. -Pu'rge~and Exhaust ,
- Isolation
'.1) - Manual Initiation 2 1 2 1, 2, 3..4 17:
2 )' . Automatic Actuation 2 1 2 1,2,3,4 -17 Logic'and Actuation- a g -Relays ,
- 3) ' Safety-Injection See Item'l. above for all Safety Injection, initiating functions' and: ;
[ w -requirements.
- 4. Steam.Line.Is~olation . . . ,
*- a. ' Manual Initiation: .
*g p - 1) 1 System -.; . . .
~2 - .
1 . 2 1,2,3 22 Y-
- g 2); <ledividual - 1/ steam'line 1/ steam line 1/ operating- 1 , 2 , 3 _. 23 'Ng
. . steam line g.
2- 21 , gg - b. Automatic Actuation 2 1 41 , 2 ,; 3 " Lq :
' f<
22
- Logic and Actuation -
.o .o Relays
' 8 c. ~ c. Costainment' Pressure . 4' .2- -3 ' 1', 2, 3 16 Z High-High 3/ steam line:. 2/ steam line' '2/ steam ifne~ 15
.. Steam Line. Pressure- 1, 2, 3# -
$$.l l~
'. 'd . . . '
lin any stearn . e r+ .. Low <
-line
-l g 7 v'n4 -ge. ,- .
py+ y.. 7 W y % gg g W g. ,w,g.p9 - 9-g. ,_y- ggy yand,gr- g- , $ N3h
~
TABLE 3.3-3 (Continued) E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION c 5 MINIMUM d TOTAL NO. CHANNELS CHANNELS APPLICABLE
- FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 4. Steam Line Isolation (Continued)
- e. Steam Line Pressure - 3/ steam line 2/ steam line 2/ steam line 3## 15 Negative Rate-High in any steam line
- 5. Fcedwater Isolation
.2. I w a. Automatic Actuation 2 1 2 1, 2 27 -l 1 Logic and Actuation u Relays E b. Steam Generator 4/stm. gen.
2/stm. gen. 3/stm. gen. 1, 2 19 Water Level . in any oper- in each oper-High-High (P-14) ating sim. ating stm. gen. gen.
- c. T g
_ Low (p_4 (( interlock) 4 2 3 1, 2 19 Ei d. Doghouse Water 82 Level-High .2/ doghouse 1/ doghouse 2/ doghouse 1, 2 27 F
' A% in any doghouse y EE
- e. Safety Injection See Item 1. abovt'for all Safety Injection initiating functions and requirements.
- 6. Turbine Trip EE
;3;7 a. Manual' Initiation 1 1 1 1,2 25 E b. Automatic Actuation' ' '
Logic and' Actuation: Af Relays: 2 1 !2 1,2 27 l s
n TABLE 3.3-3 (Continued) ENGINEERED' SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5 E MINIMUM U TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION [ [ 6. Turbine Trip (Continued)
- c. Steam Generator Water Level-High-liigh (P-14) 4/stm. gen. 2/stm. gen. 3/stm. gen. 1,2 19 in an/ in each operating stm. operating stm.
gen. gen.
- d. Trip of All Main Feedwater Pumps 2/ pump 1/ pump 1/ pump 1,2# 25
{
- e. Reactor Trip (P-4) 2 'l 2 1,2,3 22 i
- f. Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.
. ,, 7. Containment Pressure Control System fgg k[
33
- a. Start Permissive 4/ train 2/ train 3/ train 1, 2, 3, 4' lb6
{$ a3
- b. Termination 4/ train 2/ train 3/ train 1, 2, 3, 4 (( 8. Auxiliary Feedwater OO
- a. Manual Initiation ~ 1/ train- 1/ train 1/ train 1, 2, 3 - 26
^^ b. Automatic Actuation Logic 2 1 2 1,2,3 21
~ $ $ ', and Actuation Relays c+ e
_ . . . _ _ . . _ . .-. = 1 __ . . . _ _
TABLE 3.3-3 (Continued) 9
$ ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5
E MINIMUM Q TOTAL NO. CHANNELS CHANNELS APPLICABLE
'" ACTION FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES
" 8. Auxiliary Feedwater (Continued) m
- c. Stm. Gen. Hater Level-Low-Low
- 1) ' Start Motor-Driven Pumps 4/stm. gen. 2/ste. gen. 3/stm. gen. 1,2,3 19 l i_n any opera- in each ting stm. gen. operating stm. gen.
{ . T 2) . Start Turbine-- E$ Driven Pump 4/stm. gen. 2/stm. gen. 3/stm. gen. 1,2,3 19 in any two in each operating operating stm. gen. sta. gen.
- d. Safety Injection-3.
e og Start Motor-Driven Pumps - See Item 1. above for all Safety Injection initiating functions 4
>> g y2 and requirements'. 3 3..
aa R .
.a 2 e. Loss-of-Of f site Power- Q e.
55 22 Start Motor-Driven Pumps and Turbine-Driven 4
?? Pump 6-3/ bus 2/ bus .
2/ bus 1, 2, 3 10 l .
- c. v. either bus e cn 22- f. Trip of Al1 Main L 3. Feedwater Pumps-
"" Start Motor- .OO Driven Pumps 2/ pump 1/ pump- 1/ pump 1, 2# 25
TABLE 3.3-3 (Continued) in ENGINEERED SAFETY FEATUR'ES ACTUATION SYSTEM INSTRUMENTATION f c MINIMUM E TOTAL NO. CilANNELS CHANNELS APPLICABLE d FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
, B. Auxiliary Feedwater (Continued) to g. Auxiliary Feedwater Suction Pressure-Low
- 1) CAPS 5220, 5221, 3/ pump 2/ pump 2/ pump 1,2,3 15 o-' I 5222
- 2) . CAPS 5230, 5231, l 5232 3/ pump 2/ pump 2/ pump 1, 2, 3 15 a. I
- 9. Containment Sump ca Recirculation
- 1,2,3,4
- a. Automatic Actuation 2 1 2 14 o l l
[ Logic and Actuation e Relays
- b. Refueling Water Storage Tank Level-Low 4 2 3 1,2,3,4 16
- I Coincident With
- Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.
gg E$ aa
- 10. Loss of Power-
$2 a. 4 kV Bus Undervoltage- 3/ Bus ?/ Bus 2/ Bus 1, 2, 3, 4 15 5S Loss of Voltage l IE
- b. 4 kV Bus Undervoltage-Grid Degraded Voltage 3/ Bus 2/ Bas 2/ Bus 1,23,4 15 i
! 11. Control Room Area
- yj Ventilation Operation
??- a. Automatic Actuation Logic l g .and Actualion Relays- 2 1 2 All 24 l -
. TABLE 3.3-3 (Continued) 9-
$ ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION .
g, - 2-E MINIMUM C ,. total.NO. CHANNELS CHANNELS APPLICABLE
- 0F-CHANNELS TO TRIP OPERABLE MODES ACTION '
FUNCTIONAL UNIT-s
" 11. ' Control-Room Area'
" Ventilation ~ Operation.(Continued)
- b. Loss-of-Offsite Pwer -3 2 2 1,'2, 3 .
15 a.; -
- c. Safety Injection See Item 1. above for all Safety Injections i..itiating functions and.-
requirements. ! '12. Containment Air Return and k w Hydrogen Skimmer Operation ~ j g , i w a. Manual Initiation '2 1 2 -1,2,3,4 18~ L A. i: b. Automatic Actuation ' Logic
- j. :and Actuation Relays 2' 1 2f 1,2,3,4 14h )
1. l' c. Containment Pressure-l High-High =4 .2 -3 1,2,3 16. i !' -FF 13. Annulus Ventilation Operation ' ! DE E
-@@ a. . Manual. Initiation: -2 -l' 2 1,2,3,4- _
18~ l b .- Automatic' Actuation Logic,
.&5 .and. Actuation' Relays' 2. --l' 2' 11,2,3_,4 - 14 k ._
- l.
.c. E Safety Injection : See' Item 1. above for. all(Safety Injection' initiating functions :
d
,mm :and requirements.
EE . . Sp: 14. . Nuclear' Service Water Operation l . m .-+ .
~
L .a. -Manual Initiation 2 1; 2 1,2,3,4 -18. l Automatic Actuation' Logic 1 L h. ' . fand: Actuation Relays ' ( 2 .- f g; L2 ; 11,2,3,41
] 21 a,7 ; [.,
l' l
-+m,. g w 4
~
g r rQdv.i - g <. e.. v- eu.-n g so.wr . ..k. v ,m._ -_m-. __ mu _ . _ mna
TABLE 3.3-3 (Continued) ^. 9
$. ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E
HINIMUM E TOTAL NO. CHANNELS CHANNELS APPLICABLE
] FUNCTIONAL UNIT OF CHANNELS TO TRIP' OPERABLE H0 DES ACTION
- 14. Nuclear Service Water Operation to (Continued)
- c. Loss-of-Offsite Power 3 2 2 1,2,3 ~ 15 a- }
- d. Containment Spray See Item 2. above for all Containment Spray initiating functions and requirements. -
- e. Phase "B" Isolation See Item 3.b. above for all Phase "B" Isolation initiating functions and requirements.
R f. Safety Injection See Item 1. above for all Safety Injection initiating functions [ and requirements. A
- g. Suction Transfer-Low ,
Pit Level (Units 1 and 2)
-1) 1 Out Of 2 Logic 2/ pit 1(cither 1/ pit 1,2,3,4 20* '
Pit) ) 3/ pit
-G)- 2 Out of 3 Logi F 2/ pit (either 2/ pit 1,2,3,4 29' ,
pit) EE a= 15. Emergency Diesel Generator h yE Operation (Diesel Building o ?. Ventilation: Operation, Nuclear 55 Service Water Operation) .
-fy a. Manual Initiation' 2 1 2 1,2,3,4 18 y b. Automatic Actuation-Logic and Actuation Relays 2 1 2- 1,2,3,4 21 -((
- c. Loss-of-Offsite Power 3 2. 2 1,2,3,4 ~ 15 0., .l
- d. Safety Injection See' Item 1. above for all Safety Injection initiating functions
. DC and requirements.
- 16. Auxiliary Building. Filtered Exhaust Operation
- a. Manual Initiation 2 I 2 1,2,3,4 18-
- b. Automatic Actuation'i09 i c 1 2- 1.2.3.4 '2I" and Actuation Relays 2
IABLE 3.3-3 (Continued) b ENGINEERED SAFETY IEAlURES AC10AT10N SYSIEH INSlRUMENTAll0N 2,
. 63 e
MINIMUM c: TOTAL NO. CilANNELS CHANNELS APPLICABLE
'i IUNCTIONAL UNIT OF CHANNELS 10 1 RIP OPERABLE H0 DES ACTION
-e
- 16. Auxiliary Building filtered y
"* Exhaust Operation (Continued) >
N
- c. Safety Injection See item 1. above for all Safety injection initiating functions and requirenents.
- 17. . Diesel Building Ventilation Operation
- a. Manual Initiation 2 1 2 1, 2, 3, 4 18 t'_ b. Automatic Actuation Logic
** and Actuation Relays 2 1 2 1,2,3,4 21as l w
d> c. Emergency Diesel Generator Operation See ! tem 15. above for all Emergency Diesel Generator Operation initiating
. functions and requirements.
18. Engineered Safety features
' Actuation' System Interlocks 2, 2, a. Pressurizer Pressure, 3 2 2 1,2,3 20 W$
ao P-ll
$IEI b. Pressurizer Pressure, 3 2 2 1, 2, 3 ' 20 8$
ee not P-11 zz c. 4 2 3 1,2,3 20 oo Low-Low Iavg, P-12
- d. Reactor 1 rip, P-4 2 2 2. 1,-2 3- 22 4
- -s e. Steam Generator Water 4/sta.-gen. 2/sta. gen. 3/sta. 1, 2, 3 - 20 EF Ei ~ Level, P-14 in any gen. in
;;;;" operating each n, r. stm. gen. operating
stm. gen.
l TABLE 3.3-3 (Continued) , TABLE NOTATIONS
# Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) setpoint.
## Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked. l
'T visions of this Action Statement may be waived for up to :
per pit to the implementation of the mo titr o change the ; Nuclear Service Water swa - i ut of 3 logic system. l
** Applicable gafteemen ation of the modi c install the 2 out '
_, p gic systam. ACTION STATEMENTS l ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY g r within 4 hours and in COLD SHUT 00WN within the following p 30 hours; however, one channel may be bypassed for up to 4 hours for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE. ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within la hWS -1 hcur. l ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 2-hours for surveillance testing per l Specification 4.3.2.1. i ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed. ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTOOWN within the following 30 hours. ACTION 19 - With the number of OPERABLE channels one less than the Total-Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the follcwing conditions are satisfied:
- a. Ths inoperable channel is placed in the tripped condition within 1 h m , and l 6 Awf5 Y
- u. TheMinimumChannelsOPERABLErequirementishet;however,ce-additional channel may be bypassed for up to hours 'for sur- l veillance testing of other channels per Specification 4.3.2.1 CATAWBA - UNITS 1 & 2 3/4 3-25 Amendment Nc. [(Unit 1)
Amendment No. (Unit 2)
1 TABLE 3.3-3 (Continued)- ! ACTION STATEMENTS (Continued) ACTION 20 - With less than the; Minimum Channels OPERABLE, within 1 hour determine by observation of the associated permissive status- , light (s) that the-interlock is in its required state for the ' existing plant condition, or apply Specification 3.0.3.- l l ACTION 21 - With the number of OPERABLE chinnels one less than the Minimum-reffoM #-A M annelis OPERABLE withi requirement,%be hours in at least 00WN and in at-least HOT-SHUT HOT STANDBY within the following- & nacl T3 of6 ,g Advr # 0 forhours; however, surveillance one per testing channel may be 4.3.2.1 Specification bypassed for upthe provided to h .I-other channel is OPERABLE. ACTION 22 - With the number of OPERABLE channels one less than the Total do M Number of Channels, restore the inoperable channel to OPERABLE status within'48 hours or be in at least HOT STANDBY within 6 hours and in at least HOT SHUTDOWN within the following 6 hours. ACTION 23 - With the number of OPERABLE channels one less than the Total. Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or declare the associated valve inoperable and take the ACTION required by Specification-3.7.1.4. ACTION 24 - With the numoer of OPERABLE channels one less than the Minimum Channels OPERABLE, restore the inoperable channel to OPERABLE status within 48 hours, or initiate and maintain operation of the Control Room Area Ventilation System with flow through the HEPA filters and activated carbon adsorbers. ACTION 25 - With the number of OPERABLE channels one less than the Minimum
. Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours. -
ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours and'in at least HOT SHUTDOWN within the following 6: hours. ACTION 27 - With the number of OPERABLE ' channels one less than the Minimum Channels OPERABLE requirement be in at least HOT-STANDBY within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE. ACTION 28 a. With the number of OPERABLE channels one less than the 1 Number of Channels, restore the inoperable c el g g* to 0 LE status within 7-days or align the ear Service Wa System for Standby Nuclear ice Water Pond recircula ' , or be in HOT STA within the next-6 hours 4 and in at . t COLD SHU N within the-following 30 hours.
- b. With the number of 0 LE 2na ls one less than the Minimum Channel P RABLE requireme within 1 hour align the Nuclear rvice Water _ System for Sta Nuclear Servic ater Pond recirculation, or be in T TANDBY w' n the next 6 hours and in at least COLD SHU N--
ithin the following 30 hours. CATAWBA - UNITS 1 & 2 3/4 3-26 6endment No. /(Unit 1) Amendment No. ' (Unit 2)
go ct(Avarr TABLE 3.3 3 (Continued) N f**
-TABLE NOTATIONS ,
ACTION 29 - With--the number of OPERABLE' channels less than the-Total Nuxber
'of Channels, STARTUP and/or POWER OPERATION may proceed provided one of the following applicable conditions is satisfied:1
- a. With one channel inoperable, place the inoperable channel ~
in the tripped condition within 4 hours and ensure the-Mininum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 2 hours for surveillance testing of other channels per Specifica-- tion 4.3.2.1; or
- b. With.less than the Minimum Number ofLChannels OPERABLE align the Nuclear Service Water System for Standby Nuclear-Service Water Pond recirculation within 4 hours, or be in i at least HOT STANOBY within the next 6 hours,-at least HUT. 1:
SHUT 00WN within the following 6 hours, and at least COLO l -- SHUTOOWN within the subsequent 24 hours. CATAWBA - UNITS l'& 2 3/4 3-26a Amendment No.59 (Unit 1)- Amendment No.52 (Unit 2)
.= :.
TPtr.rff APDmoNAt Acr(oMl sr&TegeurIL.ro 6E14YtercTFA rod LostWL T\ tt. stG;rfEc.Tt v6*U - WVMdG7tSO hcrioUi CMTVMSA/r5 L
.Aci<cu l % ~ Victh 4 avnder b-(: 0f6M6L5 cknacl5 oac kn Than tk aksnhvw Gkanacds 0767M6uV <9vereinnt,
- h. in a+ les& ; HOT KTAWP0'l luctide. 8 hovrt anS is cotD znaT90dN . dctho*^ +Le -follow?rty .10 bo'va;.
h owever, 0:1c. chwrunel enel .lc. bytnuch.I for of fu _
.2..
_fCkc.a.$$0n- 0 o A 1., },} k our? -{~0r EUrVk.1l Nacs YC1'f1h] fCr S C prehAl -rte. der ekanacj i< s(eM6L6~, . Acn ow n+ b - kehL A ovolv af senMer ekanelt one:ka:ttan;
~
i ka. A A ,'n , % ,n. Clunns{r otsuGLS regvwenest, b: K at Ice.& ser srnupst &c1% 0 kourt anl {s coco: mAJT9owN v n-tG. tk -(,IIowin, da 4over; h u ncj ont chnnel <w k. 6ypaael Ae . ar
- A A ever
-for rurvd Ihaeo +srtins fcc .QecK15~3 1.1.,1, froh0e$ rix. 0+Lcc ekanns) is of8An 0W.
ska -tk Toh d 'Afurnbv. af channelt, opera.+?ar m , froeeel va+ii fe.c&rmncu e-F th ne*+ ryvirL AWA1.oc cMWWGL ofeDWnbdAL RETT' fro 5)cS 1Av , 1Aspcado cimarel ir ; lace.0. 1% k ;fri[yck canZ4& cAfG 1 6our . Acricv &a- Netl~ A : nv,4.e of of'6?St6te c Annaclr o,o ku f4an
~
, . A 'Tk( Nander e-P Chanac.fr, etcadEs~ w fro w $
.proE0eS %. s'nspnLLv ck anatel h p\a a L in A (>ipexd
A _ - .p.-- fL , m C )
- a. .
s j '. ' _ q. 4 . +.;gQ.,
. , . - -+ ..
rephed in mA. One aAL%ind(Jhennul%n .
. _' - ;bekexuekfch(:J%t.; 40r.r$ .r vrvit Lnn . =- +ts%j p.cfedc6Uh b4 'n. 7. L.'I.J ~ .
a - g ,, I tha fia Tc1=l %.skr & ChanncJr, smieTuf ' , an0l0( ?o svaY(, .OfGR&T1oV n s-ftvcee0-pror~<SSYic.. t . . - Mio~;ay canRhinure :sardel :. = - . : a, 7k. inog.cauu:danncl irg/nAT/4 :fk!7rddi [ co aWen JL 1 in c ur, ank - L. A e a a ;c6nnJr:oearugt. % acr.mc4 A l me.+p bowe.vre,;one aaskhikt 6anad%.yle.: . hyraucL se : ve. i+ A h urr M c;ceckd(d w .
~
arm :y 4 o1 Ace cleane/r. per;QedcAdh ce 4,7,1.C f
'e +
,-+g
- 9. h
; b b~ . b m_D W M : h .; ka $ oO . S hi.
-N i6i\VSW C Knnb y OfW$$.YCf clsnt%% e.l l*G -~ i c& teart ion .mwnta&csucrwh u% .
- Ind JHcr KnuTDowV Mi&-k f(&TnjG4h over;; . .
~
,. .:. b _- b .-. .
k ,_ ., S ri cvcve. & w fes %f4cr XpccR;io~%%.tlIL ^:, . frohjck n oth eknet is ofc1% ear.. . . , . u - . . : .. w N: - ,,w'.'4 4 <,w w f 46 g u + . 2- _
-.Jg _.ij ., m - -,, , ~. ,,
ve+a ,. , -
Q g TABLE 3.3-4 For Unit 1 , ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS c FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 5 d 1. Safety Injection (Reactor Trip,
- Phase "A" Isolation, Feedwater C Isolation, Control Room Area Ventilation Operation, Auxiliary Feedwater-Motor-Driven Pump, Parge & Exhaust Isolation, Annulus Ventilation Operation, Auxiliary Building Filtered Exhaust Operation, Emergency Diesel Generator Operation, w Component Cooling Water, 1 Turbine Trip, and Nuclear > Service Water Operation)
- a. Manual Initiation N.A. N.A.
- b. Automatic Actuation Logic H.A. N.A.
and Actuation Relays
- c. Containment Pressure-High $ 1.2 psig 5 1.4 psig e d. Pressurizer Pressure-Low -> 1845 psig -> 1839 psig am aa 2M e. Steam Line Pressure-Low -> 775 psig -> 744 psig an ,a ,
z2 2. Contain:nent Spray ?' =y s ?? -O Manual Initiation N.A. N.A. ISS
- a.
[32j m 22
- 3. 3.
- b. Automatic Actuation Logic and Actuation Relays N.A. N.A. ' N6 c
, TRIP SETPOINT ALLOVABLE VALUE FUNCTIONAL UNIT C
5 3. Containment Isolation d a. Phase "A" Isolation g C N.A. N.A. .
- 1) Manual Initiation
- 2) Automatic Actuation Logic N.A. N.A.
and Actuation Relays
- 3) Safety Injection See Item 1 above for all Safety Injection Setpoints and Allowable Values.
m b. Phase "B" Isolation (Nuclear Service Water Operation)
}
N.A. N.A. [. 1) Manual Initiation E '2) Automatic Actuation N.A. N.A. Logic and Actuation -
, -} R Relays r#l
,'M nj
- 3) Containment Pressure- 1 3 psig i 3.2 psig High-High I1 EE Q b. b
- c. Purge and Exhaust Isolation gd N.A. N.A. ,
'N 1) ' Manual Initiation EE 2) Automatic Actuation _ N.A. N.A.
Logic and Actuation g9 Relays-
- 3) Safety. Injection See Item 1. above for all Safety Injection Setpoints and Allowable */alues.
== -
~
n ' TABLE 3.3-4 For' Unit 1 (Continued) 3> ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION TRIP SETPOINTS l6- , [ FUNCTIONAL UNIT- TRIP SETPOINT - ALLOWABLE VALUE
-j 4.SteamLineIsolatibn .
3 a. Manual Initiation N.A. N.A. , jf, b. Automatic Actuation Logic N.A. N.A. N and Actuation Relays
- c. ' Containment Pressure-High-High < 3 psig' < 3.2 psig-
- d. Steam Line Pressure - Low > 775 psig > 744 psig e .- Steam Line. Pressure- -< 100 psi -< 122.8 psi"*
Negative Rate - High
- 5. Feedwater^ Isolation
$ ' a. Automatic Actuation Logic- N. A.' N. A. -
.,_ Actuation Relays w b. Steam Generator Water
- g. . Level-High-High.(P-14)
- 1. Unit 1 < 82.4% of < 84.2% of narrow iiarrow range range instrument instrument- Espan -I
- span .,,
Wy . gg 2. . Unit 2 < 77.1% of- L< 78.9% of narrow
.g* narrow range : range instrument ?
gg instrument . span gd;l-g 7' gg span. , 4 ((' r.. - T,yg-Low > 564*F- >L561*F-PP
}
- d. - - Doghouse Water Levei-High .11_ inches- , 12. inches w . above 577 above'577' g floor level , floor . level "
EE e. - Safety Injection. .-.See-Itee l.: above for all Safety Injection Setpoints.and' Allowable Valuesa
~e . ,
f %- 'f g f-m' '\ 4 h4c' .und & as ,& xE e"" 4 mv wh k h-
.c , S + '
. .O O .,
g TABLE 3.3-4 For Unit.1-(Continued) -
. ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
. n .
. FUNCTIONAL UNIT' iUS SETPOINT . ALLOWA8LE VALUE E 6. Turbine Trip M a. . Manual-l Initiation N.A. N.A.
p b. Automatic-Actuation N.A. M.A. N Logic and Actuation Relays c. Steam Generator Water Level-High-High (P-14)
- 1. Unit 1 -< 82.4% of ~< 84.2% of narrow narrow range ange instrument
~
. instrument - span span
$ 2. Unit 2 < 77.1% of .5 78.9% of narrow 3 narrow range. range instrument -
- w. instrument span a
o span-
- d. Trip.of All Main' N.A. N.A. <
Feedwr.er Pumps
- e. Reactor Trip:(P-4) ' N.A. N.A.
- f. Safety; Injection. ~See Item 1. above for.all Safety Injection'Setpoints and Allowable.
lfk '
- Values. .h 7. Containment Pressure Control- .g 3 System' = $[
00 *
- a. Start Permissive; 5.0.4 psid < 0.45lpsid -h-.
A
.g.g b.- Termination '- > 0.3 psid. > 0.25 psid : ; ;
82 8.l Auxiliary Feedwater , Kg 'i
- $h a. Manual Initiation'- N. A - '
N.A.
- k. t EN L b. - ' Automatic Actuation Logic- . N.A. M.A. %9 mg:
'and Actuation Relays
~
f}: 3 4
' , e
< .m , a e ~, r, ., , - + ~ ~ , s ww - , , ,. ~,, - - . . . -
n TABLE"3.3-4 For Unit 1 (Continued) Y ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 2 FUNCTIONAL UNIT TRIP SETPOINT ALLOWA83LE VALUE [8. Auxiliary Feedwater (Continued)
- c. Steam Generator' Water M Level. -' Low-Low
' If.
" - 1) Unit 1 > 17% of span > 15.3% of from 0% to span from 0% to 30% RTP 30% RTP increasing .---.
increasing linearly to linearly to ..1 38.3%'of span
> 40.0% of from 30% to 100%
span from 30% RTP to.100% RTP w 2) Unit 2 > 36.8% of > 35.1% of narrow . A iiarrow range range instrument
> span .
span .
- d. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
w
- e. Loss-of-Offsite Power . > 3500 V 1 3200 V
- f. Trip of All Main'Feedwater Pumps N.A. N.A.
- g. Auxiliary Feedwater Suction gg Pressure-Low ,.
gg 1) CAPS 5220, 5221, 5222 > 10.5 psig > 9.5 psig- ( 2R 2) CAPS 5230, 5231, 5232 -> 6.2 psig- > 5.2 psig - i ~
- EE -a. Unit 1 [6.2psig - [5.2psig ' 11 zx oo
- b. Unit 2
~
1 6.0 psig. +
't 5.0 psig . 'd l-
* ~ ; 9. Containment Sump Recirculation
]
(3. . gg g p[
$3 -a. Automatic' Actuation Logic- N.A. N.A. ..k
- and Actuation Relays:
-22
- hh b. Refueling' Water ~ Storage 1 177.15 inches > 162.1 inches my. -Tank Level-Low . . '
Coincident W1th Safety- . . Injectio'n ' See: Item 1..above for all Safety Injection Setpoints and Allowable Values.~. t#- m -F +
+ w w v s e + m . 2_ .+_u_2 __ _.a__.1.._ m.._m.
TABLE 3.3-4 For Unit 1 (Continued) , n D
> ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 6
TRIP SETPOINT ALLOWABLE VALUE I FUNCTIONAL UNIT C
$ 10. Loss of Power d a. 4 kV Bus Undervoltage-Loss 3 3500 V 2 3200 V g _j g of Voltage
- b. 4 kV Bus Undervoltage- 1 3685 V 1 3611 V Grid Degraded Voltage
- 11. Control Room Area Ventilation Operation
, a. Automatic Actuation Logic and Actuation Relavs N.A. N.A.
}
[. b. Loss-of-Offsite Power 1 3500 V 3 3200 V U c. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
- 12. Containment Air Return and Hydrogen Skimmer Operation
- a. Manual Initiation N.A. N.A.
~((
- s a S@ b. Automatic Actuation Logic N.A. N.A. d2C'
^
( and Actuation Relays ,
%% ~
- c. Containment Pressure- 5 3 psig $ 3.2 psig l
[f Y- ! wG High-High nf' G m4 l %% M l FF l 33 St'
p ~ M: n TABLE 3.3-4 For Unit 1 (Continued) s
- 1. > -
_ ENGINEERED SAFETY FEATURES' ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
>- y
.. FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE C
i'i 13. Annulus' Vent 11Etion Operation - 2 l
%' a. Manual Initiation - N.A. N.A. _.
E .
- b. Automatic Actuation Logic ' N.A. N.A.
and Actuation Relays c.. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable. Values. 14.-Nuclear Service Water Operation w a. ' Manual Initiation N.A. h. A. 2 . . .
- >- b. -Automatic Actuation Logic N.A. N.A.
.w and Actuation Relays O
- c. ' Loss-of-Offsite Power ' 2 3500 V . 1 3200 V-d .- Containment Spray- See Item 2. above for all Containment Spray Setpoints and Allowable Values. . -
- e. Phase "B" Isolation - See Item 3.b. above for all. Phase."B" Isolation'Setpoints and Allowable.
Values. 82 . ..
. Safety Injection
- f. . See Item 1. above for. all Safety Injection.Setpointsf and A110wable' Values.
I"3.& 33 g. Suction' Transfer-Low Pit Level E-1 l. 554.4 ft.' ZE1. 552.9 ft.
-2z t.g'
..i PP ~ 15. -Emergency G Nsel Generator-Operation (Diesel Building- .
?n 1 ' Ventilation Operation, Nuclear- ' t%O Og ' -Service Water. Operation)'- .*
. " 3.
'"". Ea.
Manual .' Initiation' N.A. N.A. i p @ge..W - N .-- M. 7% ';" *
,tt' r
( a 991 9 'y- 'br
#" % 4 % * * ' "9*9-T ' '4' W A--re-
n TABLE 3.3-4 For Unit 2 (Continued) M ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP SETPOINT ALLOWABLE VALUE
. FUNCTIONAL UNIT k 15. Emergency Diesel Generator d Operation (Diesel Building Ventilation Operation, Nuclear E Service Water Operation) (Continued)
Automatic Actuation Logic N.A. N.A. b. and Actuation Relays
> 3500 V > 3200 V
- c. Loss-of-Offsite Power _
Safety Injection See Item. I above for all Safety Injection Setpoints and Allowable Values. d.
$ 16. Auxiliary Building Filtered
> Exhaust Operation N.A. N.A.
- a. Manual Initiation Automatic Actuation Logic N.A. N.A.
b. and Actuation Relays Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values. c. i I kk 17. Diesel Building Ventilation gg Operation ' 8m N.A. N.A.
-3g a. Manual Initiation zz Automatic Actuatica Logic N.A. N.A.
.o .o b.
g , and Actuation Relays w- See Item 15. above for all Emergency Diesel Generator Operation gg c. Emergency Diesel Generator 3g. Operation Setpoints and Allowable Values. cr 11
&& q ,
+
} %$l
$G I
~~'
)b
a . TABLE 3.3-4 For Unit 1 (Continued). A/O C(@N66% TABLE NOTATIONS Nb ' u
**The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate-High is greater than or equal to 50 seconds'.
Channel calibration shall ensure that this time constant is adjusted to this value. i I i
-I i
i CATAWBA - UNITS 1 & 2 3/4 A 3-36 Amendment No.101 (Unit- 1) l Amendment No. 95 (Unit 2) l-
N
~
'h..
r, TABLE'3.3-4 For Unit 2- -[ .
--M g ' -
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS q h FUNCTIONAL UNIT ' TRIP SETPOINT 'ALLOWA8LE VALUE a , 1 1. Safety .Injectienl(Seactor Trip, L
' Phase:"A">Isolatten, Feedwater.-
- Isolation, Control'Asom Arm -
Ventilation Operation, Auxiliary
,Feedwater-Motor-Driven Pump, Purge & Exhaust Isolation, Annulus $-
Ventilation Operation, _ .
. Auxiliary Building Filtered
- Exhaust Operation,, Emergency -
Diesel Generator Operation - ' w Component Cooling Water,-
') Turbine Trip...and Nuclear' ~*'
= c. : Service Water Operation)- .
a..
^
, Manual Initiation .N.A. M.A.
'b. Automatic Actuation' Logic ;N.A. N.A. _ V and Actuation Relays--~ - "E p -c. ContainmentPressure-Highf "i 1.2 psig : 1 1.4 psig f[
oa
- d. Pressurizer Pressure-Low. > 1845 psig.
-> 1839 psig'.
j- Ik. gg
. e..
Steam Line Pressure-Low 4 1 725 psig' :> 694 psig*- l g 22 2. Containment Spray' .
.. l VM g
- pp ' .
y3 ~ Manual' Initiation' 1N.A. u, -
- a. . ' N. A. .
S, c\
-b[ -Automatic Actuation Logic.
~
' gg - M.A.; -. N. A. .
%=
. = n., and Actuation Relays 1 -
4 V ~c *? . . . . . . . [; 20 1 c. s _ Containment Pressure-High-High . i'3 psigL 1 3.2 psig-l F
.. c--
.-n, ,
, ..a, q , _; '
sL
. sly .,.' Y*
n
-TABLE'3.3-4 For Unit 2 (Continued)
~
['
-g . ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION TRIP SETPOINTS
' FUNCTIONAL UNIT , TRIP SETPOINT' ALLOWABLE VALUE -
C~
- 3. Containment Isolat. ion i
- e. a. Phase'"A" Isolation C
- 1) Manual Initiation M.A. N.A. . . .
- 2) Automatic Actuation Logic . N.A. N.A.
and Actuation Rel es
- 3) Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
w b. Phase "B" Isolation (Neclear i . Service Water Operation)' - oz ~ w 1) . Manual Initiation N.A. N.A.
- 72) Automatic Actuation M.A. .N.A.
Logic and Actuation Relays N 3 Cr l n g1
~3) Containment Pressure- 5 3 psig. 5 3.2 psig I 1' gg
~'
- High-High 1' y p
c.
^
Purge and Exhaust Isolation.
.4 1 5 :1)" Manual : Initiation N.A.. N.A.. ,
xz
- PP-
- 2) Automatic ' Actuation L N.A. 'N.A.
Logic and Actuation g-m- Relays.
' EE
- 3.3. 3) Safety Injection; -
See Item 1.:above-for all Safety Injection Setpoints and Allowable Values.. ee
]f, ' .-
i e g 4 g ,y., f y-v -vvr' :s i e 4 e e =++- *-
4 d 'J' ci . > .
r-
. .. . i i . ,
3 . .
~
. TABLE 3.3-4 For Unit 2 (Continued) -- 5;
-a g, . ENGINEERED' SAFETY FEATURES ACTUATION SYSTEM INSTRtMENTATION TRIP SETPOINTS' g 7 . FUNCTIONAL UNIT.-
TRIP SETPOINT. ALLOWABLE VALUE . 4 '4.' Steam Line Isolation .- > ._ . d N.A.
- a. : Manual, a:Inqw. ion M. A. . .r 1+1
. g. g' - y
" - b. Automati : Actuation Logic' N.A. N.A. 4 I. and Actuation' Relays 4 "
. c. ' Containment Pressure-High-High ~1 3 psig $ 3.2 psig' ,
=d. : Steam Line' Pressure - Low' 1 725 psig . l'.694 psig* . ~[
4-
< 100 psi
- e. LSteam Line Pressure-- ~
-< 122.8' psi **
Negative Rate'- Highl ,, , 5. Feedwater. Isolation P ;) 'a . Automatic Actuation Logic- N.A. N.A. 4 l Actuation Relays a, ; 4" y ti. Steam Generator Water g- Level-High-High (P-14). -fg
'1. . Unit 1: < 82.'4% of. <-84.2% of narrow Y Harrow range range' instrument $4
- instrument. span: ,W9
' span -
fi O - , 2 gg "2. ' Unit.2 < 77.1% of- ' < 78.9E of narrow - -
. *g . : narrow range ~ range, instrument I
>.M@ .
, instrument- h, 1 span-span;
~
.k ,
t
- c. .
- > 564*F >'561*F- #
.. g g - "T-avg-Low - -
- d. Doghouse Water Level-High 11. inches ~12 inches '
e o. . above 577. labove 577'1
- C' ec.
- floor.leveli floor. level-a L = s,L m e. . Safety Injectionc :
See Item 1.Jabove for al1 Safety Injection Setpoints:.and-Allowable Values.? 3
<+ e
~ '
2C
;ug;.;,;
~
',r
,-yN; L
f
~
,n- 2
< , .~ +wu w - .. :.'. ~ .= ; - _ . - . a _ : a _ _i - :=..: _a - 2: L . . . - .
~ ,
I TABLE 3.3-4 For Unit 2 (Continued) , g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
. FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE E 6. Turbine Trip -
d- Manual Initiation
~
- a. M.A. N.A.
l y b. Automatic Actuation N.A. N.A. Logic and Actuation Relays
~
- c. Steam Generator Water -
Level-High-High (P-14)
- 1. Unit 1 ~< 82.4% of < 84.2% of narrow narrow range range instrument instrument span span 1 2. Unit 2 < 77.1% of
. < 78.9% of narrow m iiarrow range range instrument '
w instrument span g span
- d. Trip of All Main N.A. N.A.
Feedwater Pumps
- e. Reactor Trip (P-4) N.A. N.A.
g f. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable
. . . Values.
fh
- 7. Containment Pressure Control s System ee .
22 a. Start Permissive < 0.4 gisid < 0.45 psid OO Termination 1 0.3 psid 4 eo _. b. 1 0.25 psid y m -* 8. Auxiliary Feedwater
- 4 nn ,
v, n , i t x-i
&& a. Manual Initiation N.A N. A.'
g7 U Automatic Actuation Logic SC. b. and-Actuation Relays H.A. N.A. Ig"hL . o> V)
.I TABLE 3.3-4 For Unit 2 (Continued) 9;' ENGINEERED SAFETY FE?.W RES ACTUATION SYSTEM IMa N NTATION TRIP SETPOINTS TRIP _.TPOINT ALLOWABLE VALUE h FUNCTIONAL 13IT
' 8. Auxiliary Feedwater (Continued) c
?! c. Steam Generator Water g Level - Low-Low g 1) Unit 1 2' 17% of span 1 15.3% of
" from 0% to span fror.0% to
- 30% RTP 30% RTP facreasing increasing linearly to linearly to 1 38.3% of span
> 40.0% of from ?O% to 100%
span from 30% RTP to 100% RTP
- 2) Unit 2 1 36.8% of 1 35.1% of narrow w
N narrow range range instrument - l
- span .- span Safety Injection See Ites 1. above for all Safety Injection Setpoints and Allowable Values.
Y 4. U e. Loss-of-Offsite Power 1 3500 V 1 3200 V
- f. Trip of All Main Feedwater Pumps N.A. N.A.
- g. Auxiliary Feedwater Suction Pressure-Low gg 1) CAPS 5220, 5221, 5222 1 10.5 psig 1 9.5 psig dg{
1 6.2 psig 1 5.2 psig (gj kk g-p 2)' CAPS 5230, 5231, 5232
- a. Unit 1 1 6.2 psig 1 5.2 psig ,
g/ i 1 5.0 psig a 16.0 psig ' g$ 1 xz
- b. Unit 2
?P_.9.
N Containment Sump Recirculatior. pl [l gg
- a. Automatic Actuation Logic and Actuation Relays '
M.A. N.A.
%[ -
Refueling Water Storage hh b. Tank Level-Low 1 177.15 inches 1 162.4 inches vv Coincident With Safety Injection See Ites 1. above for all Safety Injection ' 1soints and Allowable Values. E e- 4
l r3 TABLE 3.3-4 For Unit 2 (Continued) - a g ENGINFER.V SAFETY FEATURES ACTUATION SYSTEM INSTRIMENTATION TRIP SETPOINTS
> ALLOWABLE VALUE a FUNCTIONAL UNIT TRIP SETPOINT
=
C
- 10. Loss of Power ' -
w g a. 4 kV Bus Undervoltage-Lo'ss -> 3500 V ~> 3200 V E of Voltage
- b. 4 kV Bus Unde,rvoltage- > 3685 V > 3611 V Grid Degraded Voltage
- 11. Control Room Area Ventilation Operation w a. Automatic Actuation Logic and Actuation Relays N.A. N.A.
)
co i > 3500 V > 3200 V w % b. Loss-of-Offsite Power e 3 See Iter 1. above for all Safety Injection Setpoints and Allowable
~" 1 c. Safety InfaTiion Values.
12.* Containmer Air Return and Wdrogenseximmer Operation Mr.iual Initiation N.A. N.A. -k2 oo 2 a. kk b. Automatic Actuation Logic snd Actuation Relays M.A. N. A.
-I h SS j AC zz
?? c. Containment Pressure- S 3 psig i 3.2 psig (Gn .; 4
/
g High-High l9g" j m-se
==
'Qfi ce [
OU
3 g TABLE 3.3-4 For Unit 2 (Continued) l. . $ ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTMBENTATION TRIP SETPOINTS g
- FUNCTIONAL UNIT. TRIP SETPOINT. ALLOhMBLE VALUE E I q 13. Annulus. Ventilation Operation m- .m #.
w a. Manual-Iait$attea N.A. N.A. e
.C
- b. Automatic Actuation Logic M.A. N.A.
and Actuation Relays j. , c. Safety Injection: See Item 1. above for all Safety Injection Setpoints and Allowable Values. L n. !, 14. Nuclear Service Water Operation i a. Manual Initiation N.A.: N.A. ,
~
- ce b.- Automatic Actuation Logic ' N.A. N.A.
w and Actuation Relays ! w
- c. - Loss-of-Offsite - Power -
> 3500 V.- > 3200 V-l d. Containment Spray See Item 2. above for all Containment Spray Setpoints and A:1emable Values.
- e. Phase'"B" Isolation 'See Item 3.b. above for all Phase "B" Isolation Setpoints and A11eumble Values.
- f. Safety Injection See Item 1..above for all Safety Injection.Setpoints'and Allowable Values..
Ea g. Section Transfer-Low Pit Level >E1. 554.4 ft. >E1. 552.9 ft.
- g *z j
- ...' 15. Emergexy Diesel-Generator, e& Operation (Diesel Building f. -lL Y Ventilation Operatieng Nuclear f.tcI
%S!
! E2 . Service Water Operation) . 11 - t ( p- }qk 1 - a.- Manual Initiation M.A. M. A.- - 06 N .j = g- [
= . _ . .. _ . _ . . _ . . . , . . . . ._- , - - . _ - . . . . . ._ _ -.,__-__.._._._._-..-_.m._.. . . , ,
TABLE 3.3-4 For Unit 2 (Continued) [ , j ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS . e FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE C
~
h 15. Emerge:cy Diesel Generator - m Operation (Diesel Building ' g Ventilation Operation, Nuclear m Service Water Operation) (Continued)
- b. Automatic Actuation Logic N.A. N.A.
and Actuation Relays
- c. Loss-of-Offsite Power 1 3500 V 1 3200 V
- d. Safety Injection See Item. I above for all Safety Injection Setpoints and Allowable Values.
- 16. Auxiliary Building Filtered
= Exhaust Operation
- a. Manual Initiation N.A. N.A.
- b. Automatic Actuation Logic N.A. N.A.
and Actuation Relays I c. Safety Injection See Ites 1. above for all Safety Injection Setpoints and Allowable Values. ww 22 17. Diesel Building Ventilation RR Operation 22 55 a. Manual Initiation N.A. N.A. zz
'P? b. Automatic Actuation Logic N.A. N.A.
g ,
.and Actuation Relays w -- .
22 11
- c. Emergency Diesel Generator Operation See Item 15. above for all Emergency Diesel Generator Operation h fIj1 g c,-j Setpoints and Allowable Values.
ee - 00 h C$
,9 a g$ )3 l Rg i
b' TABLE 3.3-4 For Unit 2 (Continued) n D ENGINEERED SAFETY FEATURES f.CTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS g
> TRIP SETPOINT ALLOWABLE VALUE
. FUNCTIONAL UNIT . ':
c . 5 18. Engineered Safety Features N d Actuation SysW,Jetarlocks
- a. Pressurizer Pressure, P-11 1955 psig 11944 psig E :
Pressurizer Pressure, not P-11 1955 psig <1966 psig b.
- c. Low-Low T,,,, P-12 1553*F 1550*F
- d. Reactor Trip, P-4 N.A. N.A.
Steam Generator Level, P-14 See Item 5. above for all Steam Generator Water Level Trip Setpoints w e. - and Allowable Values. 1 .- Y M RF
- it II = o an 'a nt zz % 2 )
?? ' S3
; . Oh,
.- t 9 .,
\ p 22 oo A
$$ V
==
/Vu CLMNGR3 TABLE 3.3-4 For Unit 2 (Continued) TH(s (/1ce' I TABLE NOTATIONS
- Time constants utilized in the lead-lag controller for Steam Line Pressure-Low are t > 50 seconds and is < 5 seconds. Channel calibration shall ensure that these time constanti are adjusted to these values.
**The time constant utilized in the rate-lag controller for $ team Line Pressure Negative Rate-High is greater than or equal to 50 seconds.
Channel calibration shall ensure that this time constant is adjusted to this value. CATAWBA - UNITS 1&2 3/4 B 3-36 Amentiment No.101 (Unit 1) l Amendment No. 95 (Unit 2)
4am NoUMMWS TABLE 3.3-5 FOR UNIT 1 _ ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION RESPONSE TIME IN SECON0s
- 1. Manual Initiation
- a. Safety Injection (ECCS) N. A. ,
- b. Containment Spray H.A.
- c. Phase "A" Isolation N.A.
- d. Phase "B'F ! solation N.A.
- e. Purge and Exhaust Isolation N.A. .
- f. Steam Line Isolation N.A.
- g. Diesel Building Ventilation Operation N.A.
- h. NuclearServiceWaterOpe/ation N.A. ,
- i. Turbine Trip H.A.
- j. Component Cooling Water N.A.
- k. Annulus Ventilation Operation N.A.
- 1. Auxiliary Building Filtered N.A.
Exhaust Operation
- m. Reactor Trip ,
N.A.
- n. Emergency Diesel Generator Operation N.A.
- o. Containment' Air Return and Hydrogen Skimmer Operation N.A.
- p. Auxiliary Feedwater . N.A.
- 2. Containment Pressure-High
- a. Safety Injection (ECCS) 1 27(1)/12(3)
- 1) ' Reactor Trip 12
- 2) Feedwater Isolation < 12 l
- 3) Phase "A" Isolation (2) h18(3)/28(4)
- 4) Purge and Exhaust Isolation 16
- 5) Auxiliary Feedwater(5) N.A.
- 6) Nuclear Service Water Operation 1 65(3)/76(4)
- 7) Turbine Trip N.A.
- 8) Component Cooling Water 1 65(3}/76(4)'
- 9) Emergency Diesel Generator Operation 1 11
- 10) Control Room Area Ventilation Operation H.A.
CATAWBA - UNITS 1&2 3/4 A 3-37 Amendment No.101 (Unit 1) ! Amende~t No. - 95 (Unit 2)
vucuwsss_
. TABLE 3.3 5 FOR UNIT I (Continued) l ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUN & TION -
RESPONSE TIME IN SECON05 j
- 2. Containment Pressure-High (Continued)
- 11) Annulus Ventilation Operation i 23 ,
- 12) Auxiliary Building Filtered N.A. -
Exhaust Operation
- 13) Containment Sump Recirculation N.A. *
- 3. Pressurizer Pressure-Low
- a. Safety Injection (ECCS) 1 27(1)/12(3) ,
- 1) Reactor Trip i2
- 2) Feedwater Isolation.' < 12 l
- 3) Phase"A" Isolation (2). [18(3)/2SI4)
- 4) Purge and Exhaust Isolation *
<6
- 5) Auxiliary Feedwater(5) N. A.
- 6) Nuclear Service Water Operation 1 65(3)/76(4)
- 7) Turbine Trip N.A.
- 8) Component Cooling Water 1 65(3)/76(4)-
- 9) Emergency Diesel-Generator Operation 5 11
- 10) Control Room Area Ventilation N.A.
Operation
- 11) Annulus Ventilation _ Operation i 23
- 12) Auxiliary Building Filtered : N. A.
Exhaust Operation
- 13) Containment Sump Recirculation N.A.
4s Steam Line Pressure-Low
- a. Safety Injection (ECCS) $ 12(3)/22(4)
- 1) Reactor Trip i 2- l
- 2) Feedwater Isolation < 12 l'
- 3) Phase "A" Isolation (2) [18(3)/28I4)
- 4) Purge and Exhaust Isolation <6
$) Auxiliary Feedwater(5) 60
- 6) Nuclear Service Water Opera ~ tion 1 65(3)/76(4)
- 7) Turbine' Trip N.A.
8)- Component Cooling Water i 65(3)/76(4)
- 9) Emergency Olesel Generator Operation 1 11- -
CATAWBA - UNITS 1&2 3/4 A 3-38 Amendment No,' 101 (Unit 1)- 1 Amendment No. -: 95 (Unit 2)- 1- % - ,, ,J,....,...'- - - - , - . . ~ - - - - . , . s
9 I 4
. . no ora,
. 71h S (MG )
, TABLE 3.3 5 FOR UNIT 1 (Continued) l ENGINEERED SAFEl'! FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS
- 4. Steam Line Pressure-Low (Continued)
- 10) Control Room Area Ventilation N.A. '
Operation
- 11) Annulus ventilation Operation 1 23
- 12) Auxiliary Building Filtered Exhaust Isolation N.A.
- 13) Containment Sump Recirculation N.A.
- b. Steam Line Isolation -
$ 10 ,
l S. Containment Pressure-High-High *
- a. Containmant Spray < 45
- b. Phase "B" Isolation 16SI3)/76(4) '
Nuclear Service Water Operation N. A.
- c. Steam Line Isolation 1 10 l
- d. Containment Air Return and Hydrogen 1 600 Skimmer Operation .
S. Steam Line Pressure - Negative Rate-High Steam Line Isolation g 10 l
- 7. Steam Generator Water Level-High-High
- a. Turbine Trip 13
- b. Feedwater Isolation i 12 l
- 8. ' T,yg-Low Feedwater Isolation N.A.
- 9. Doghouse Water Level-High Feedwater Isolation N.A.
- 10. Start Permissive Containment Pressure Control System N.A.
- 11. Termination Containment Pressure Control System N.A.
CATAWBA - UNITS 1&2 3/4 A 3-39 Amendment No.101 (Unit 1) l Amendment No. 95 (Unit 2)
=. . , AfD CRAP /6& S' TABLE-3.3-5 FM UNIT 1 (Continued) b , ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN-SECONDS
- 12. Steam Generator Water Level-Low Low Motor-Driven Auxiliary
- a. .
Feedwater Pumps 1 60
- b. Turbine-Driven Auxiliary Feedwater Pump i 60- 1
- 13. Loss-of Offsite Power
- a. Motor-Driven Auxiliary Feedwater Pumps 1 60
- b. Turbine Driven Auxiliary Feedwater Purops 1 60
- c. ControlRoomAreaVentilalianOperation N.A. ,
a
- d. Emergency Diesel Generator Operation
_ i 11
- 1) Diesel Building Ventilation Operation N.A.
~
- 2) Nuclear Service Water Operation 1 65(3)/76(4)
- 14. Trip of All Main Feedwater Pumps-
- a. Motor-Driven Auxiliary Feedwater Pumps -$ 60 [
Turbine Trip
- b. N.A. ,
- 15. Auxilitry Feedwater Suction Pressure-Low Auxiliary Feedwater (Suction Supply 1 16(6)
Automatic Realignment)
- 16. Refueling Water Storage Tank Level-Low Coincident with Safety Injection Signal (Automatic Switchover to Containment Sump) 1 60
- 17. Loss of Power ,
- a. . 4 kV Bus Undervoltage - ~
< 8.5 Loss of Voltage , ,
- b. 4 kV Bus Undervoltage- ~
< 600' -
s Grid Degraded-Voltage
- 18. Suction Transfer-Low Pit Level Nu~ clear Service Water Operation N. A. .
. CATAWBA - UNITS 1&2- 3/4 A 3 Amendment No.101 (Unit 1)>
l Amendment- No. _95 (Unit 2) .
- i D W f ] y$ % $%% hyN9 bN C: M Yv - . @
.. s . . - . ; ,' ((/OC(4/V64T gyy
** ~
TABLE 3.3-5 FOR UN!T t-y ENGINEERED SAFETY FEATUkE$ RESPONSE TIMES me- . INITI ATION $1_ ^^ AIS FUNCTION _RE$PONSE TINE IN SECONPS
- 1. Nanual Initiation-SafetyInjection(ECCS)
- s. N.A. .,
- b. Containment Spray N.A.
- c. Phase "A" !sulation N.A.
- d. Phase "B" Isol,ation N. A.
- e. Purge and Exhaust Isolation N.A. .
- f. Steam Line Isolation N.A.
- g. Diesel Building Ventilation Operation N.A.
- h. Nuclear Service Water Ope /ation N.A. ' 4
- 1. Turbine Trip- N.A.
- j. Component Cooling Water N. A. "
- k. Annulus' Vent 11ation Operetion N.A.
- 1. Auxiliary Building Filtered N. A. - ,
j_ Exhaust Operation
- m. Reactor Trip N.A.
- n. Emergency Diesel Generator Operation N.A. .
- o. Containment Air Return and Nydrogen -
Skimmer Operation - N.A.
. p. Auxiliary Teodwater N.A.
- 2. Containment Pressure-High
- a. SafetyInjection(ECCS) 1 27(1)/1253) ,
- 1) Weactor Trip 12
- 2) Feedwater Isolation <7
- 3) Phase"A"!selition(2) i gg(3)/28(4}' ,
- 4) and Exhaust Isolation <6 5)~ $aryFee6seter(5) N.A.
- 6) r Service Water Operation 1 65(3)/76(4) 1, 7) Tusine : Trip d N.A.
- 8) Component Cooling Water -1 65(3)/76(4)
- 9) ' Emergency' Diesel Generator Operation 1 11
- 10) Control Room Area Ventilation Operation N.A.
CATAWBA - UNITS 1&2 3/4 8 3-37 Amendment No.101 (Unit 1) 1 Amendment No. 95 (Unit 2)
m (\fo C % w CcS' f-TABLE 3.3 5 FOR UNIT 2'(Continued) nds /)q ENGINEERED SAFETY FEATURES RESPONSE TIMES 4 INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS l
- 2. ContainmentPressure-Nigh(Continued) ;
- 11) Annulus Ventilation Operation < 23 l
- 12) Auxiliary Building Filtered N. A.
- Exhaust Operation
]
- 13) Containment Sump Recirculation N.A.
- 3. Pressurizer Pressure Low
- a. SafetyInjection(ECCS) 1 27(1)/12(3)
- 1) . Reactor Trip i2 ,
- 2) Feedwater Isolation -
<7 '
- 3) Phase "A" Isolation (I) .
h18(3)/28(4)
- 4) Purge and Exhaust Isolation <6
- 5) Auxiliary Feedwater(5) N.A.
- 6) Nuclear. Service Water Operation 1 65(3)/76(4)
- 7) Turbine Trip N.A.
- 8) Component Cooling Water d65(3)/76(4)
- 9) Emergency Diesel Generator Operation i 11 ,
- 10) Control Room Area Ventilation N.A.
Operation
- 11) Annulus Ventilation Operation 123
- 12) Auxiliary Building Filtered N.A.
Exhaust Operation
- 13) Containment Sump Recirculation N.A.
- 4. Steam Line Pressure-Low
- a. SafetyInjection(ECCS) 1 12(3)/22I4)
- 1) Reactor Trip i2
.2) Feedwater Isolation <7-Phase "A" Isolation (2)
I4)
- 3) h18(33/28
- 4) Purge and Exhaust Isolation <6
- 5) ' Auxiliary Feedwater(5) < 60-
- 6) -Nuclear Service Water Operation _
65(3)/76(4) 7). Turbine Trip N.A.
- 8) Component Cooling Water i65(3)/76(4)
- 9) Emergency Diesel Generator Operation i 11 CATAWBA - UNITS 1&2 3/4 8 3-38 Amendment No.101 (Unit 1)
Amendment No. - 95 (Unit 2) .
{y M p % t! ;-+~ 7 &ry y ; p g n g; } >.q yzy gyp yy n &9M? wit %
}}y TABLE 3.3-5 FOR UNIT 2 (Continued) ,
6 gg g aaB ENGINEERED SAFETY FEATURES RESPONSE TIMES D . INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS
- 4. Steam Line Pressure-Low (Continued) ,
- 10) Control Room Area Ventilation N.A.
Operation
- 11) Annulus Ventilation Operation 1 23
- 12) Auxiliary Building Filtered Exhaust Isolation H.A.
- 13) Containment iump Recirculation H.A.
- b. Steam Line Isolation .
17
- 5. Containment Pressure-High-High -
- a. Containeerit Spray 5 45
- b. Phase "B" Isolation 165(3)n6(4) _
Nuclear Servica Water Operation N.A.
- c. Steam Line Isolation 17 i
- d. Containment Air Return and Hydrogen -
< 600 Skimmer Operation ,
- 6. Steam Line Pressure - Negative Rate-High Steam Line Isolation 17
- 7. Steam Generator Water Level-High-High
- a. Turbine Trip 13
- b. Feedwater Isolation 17-
- 8. T,yg-Low Feedwater Isolation H.A.
- 9. Doghouse Water Level-High Feedwater Isolation N.A. .
- 10. Start Permissive Containment Pressure Control System N.A.
- 11. Termination Containment Pressura Control System H.A.
CATAWBA - UNITS 1&2 3/4 B 3-39 Amendment No.101 (Unit 1) l l Amendment No. 95 (~ Unit 2)
Nu cFM%55 THis (Ms
' TABLE 3.3-5 FOR UNIT 2 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES i INITIATING $1GNAL AND FUNCTION RESPONSE TIME IN SECONOS
- 12. Steam Generator Water Level-Low-Low
- a. Motor-Driven Auxiliary Feedwater Pumps 1 60
- b. Turbine-Driven Auxiliary Feedwater Pump i 60
- 13. Loss-of-Offsite Power
- a. Motor-Driven Auxiliary Feedwater Pumps 1 60
- b. Turbine-Driven Auxiliary F,'eedwater Pumps 1 60
- c. Control Room Area'Ventilatioh Operation N. A. .
- d. Emergency Diesei Generator Operation 5 11
- 1) Diesel Building Ventilation Operation N.A.
- 2) Nuclear Service Water Operation 1 65(3)/76I4)
- 14. Trip of All Main Feedwater Pumps
- a. Motor-Driven Auxiliary Feedwater Pumps 1 60
- b. Turbine Trip N.A.
- 15. Auxil'1ary Feedwater Suction Pressure-Low Auxiliary Feedwater (Suetion Supply 1 16(6)
Automatic Realignment)
- 16. Refueling Water Storage Tank Level-Low Coincident with Safety Injection Signal (Automatic Switchover to Containment Sump) 1 60
- 17. Loss of Power
- a. . 4 kV Bus Undervoltage - 1 8.5 Loss of Voltage
- b. 4 kV Bus Undervoltage- < 600
~
Grid Degraded Voltage
- 18. Suction Transfer-Low Pit Level Nuclear Service Water Operation ' N.A.
CATAWBA - UNITS 1&2 3/4 8 3-40 Amendment No.101 (Unit 1) l Amendment No. 95.(Unit 2)
, . No cl4vGerf TABLE 3.3 5 (Continued) T Htt (AG.f _ _ __ /
)
TABLE NOTATIONS (1) Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish Safety Injection path - and attainment of discharge pressure for centrifugal charging pumps, ; Safety Injection and residual heat removal pumps. (2) Valves KC305B and KC315B are exceptions to the response times listed in the table. The following response times in seconds are the required values for these valves for the initiating signal and function indicated: 2.d < 30 3}/40(4)
- 3. d 7 30 3)
- 4.d {30 3)/40(4)
(3) Diesel generator starting and sequence loading delays not included. Offsite power available. Response time limit includes opening of valves to establish Safety Injection path and attainment of discharge pressure for centrifugal charging pumps. (4) Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish Safety Injection path and attainment of discharge pressure for centrifugal charging pumps. (5) Response time for motor-driven auxiliary feedwater pumps on all Safety Injection signals shall be less than or equal to 60 seconds. Response time limit includes attainment of discharge pressure for auxiliary feedwater pumps. (6) Response time includes a time delay of up to 6 seconds. CATAWBA - UNITS 1 & 2 3/4 3-41 Amendment No,60 (Unit 1) Amendment No.54 (Unit 2)
IABLE 4.3-2 a . h ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION
$ SURVEILLANCE REQUIRENENTS
' TRIP ANALOG ACTUATING MODES E CHANNEL DEVICE MASTER SLAVE FOR WHICH Q
- OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CHANNEL CHANNEL CHANNEL
" CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED FUNCTIONAL UNIT CHECK " 1. Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Operation, Auxiliary
- Feedwater-Motor-Driven Pump, Purge and Exhaust Isolation, Annulus Ventilation Operation, w Auxiliary Building Filtered D Exhaust Operation, Emergency w Diesel Generators Operation, i Component Cooling Water Turbine
" Trip, and Nuclear Service Water Operation)
N.A. N.A. R N.A. M.A. N.A. 1, 2, 3, 4
- a. Manual Initiation N.. A.
N.A. N.A. N.A. N(1) M(1) Q 1, 2, 3, 4 l b. Automatic Actua- N A.
*- tion Logic and Actuation Relays N.A. N.A. N.A. N.A. 1, 2, 3 l
- c. Containment 5 R -M-A l Pressure-High N.A. M.A.
3 .3> N.A. M.A. 1, 2, 3 l g9 d. Pressurizer 5 R -ft-Q l 2 3 Pressure-Low
% N.A. N.A. N.A. N.A. 1, 2, 3 [
- e. Steam Line 5 R -M-Q
.)qQ) Pressure-Low RR 2. Containment Spray o o N.A. N.A. N.A. 1, 2, 3, 4
' ' ' ^
- a. Manual Initiation M.A. N.A. N.A. R H.A. N.A. N.A. H.A. M(1) M(1) Q 1, 2, 3, 4
, b. Automatic Actua-f, p, tie.i Logic and
~+ .g. Actuation Relays
I Allt i 4. F 7, ( Con t i nued ) . n 3 INGINilHID SAllIY ll AIUHIS ACillAIION SYSIIM INSIRUMINIAll0N
~
~ SURVflllANCE REQtilR1MLN15 y
1 RIP
$ ANA10G ACIUAIING MODES CilANNI L 'JEVICE MASi[R STAVE I O R hilll Cil RLLAY RELAY SURVEILLANCi E CilANNlt CilANNil UPERAllGNAL OPLRA110NAL ACIUAIION TEST IS REQUIRED Z CllANNI L CALIBRAIION 11 51 1[SI LOGIC IEST 1[Si i
'" ClitCK _
IONCTIONAL UNil
- 2. Containment Spray (Continued) H.A. N.A. 1, 2, 3
" Containment 5 -
R -ft- R N.A. N. A. c. Pressure-liigh-liigh 1
'i
- 3. Containmerit Isolation
- a. Pliase "A" Isolation N.A. N.A. N.A 1, 2, 3, 4 ,
N.A. N.A. N.A. R 1:' 1) Manual Initia-
- Lion M(1) 1, 2, 3, 4
'2' N.A. N.A. N.A. M(I) Q.
- 2) Automatic Actisa- N.A.
tion Logic aind Actuation Relays
*- 3) Safety injection See Item 1. above for all Safety injection Surveillance Requirements.
- b. Phase "B" Isolation (Nuclear Service Water Operation) ~
R N.A. N.A. N.A 1, 2, 3, 4 3> 3> N.A. N.A. N.A. 3 g 1) Hassisal 1:iitia-y tion f (I 2) Automatic Actua- N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 y+ $ tion logic and g Actuationi Relays
.o
$. N.A. H.A. H.A. N.A. 1, 2, 3
~
- 3) Containment 5 R -tl- R n,
Pressure-liigh-Cc liigt:
?+b '
+ -t Purge and Exhaust Isolation gy t.
R N.A. N.A. N.A. 1, 2, 3, 4 N.A, H.A. N.A. I) ttuinal Initia-Inon
. ;i 1 Allt [ 4.3-2 (Continued) .
n- INGINilRin SAf fly li AIURIS AtlUAll0N SYSitM INSIRUM[MIAI10N D StiRVt Tit ANCi'REQOliiMN15 2- '. ~ M IRIP ANALOG ACIDAllNG M00ES CllANNil DEVICE MASlER SLAVE TOR nMICM [ CllANNil CllANNEL CilANNEL OPERAI10NAL OPERAIlONAL AC10AT10N RELAY RELAY SURVEILLAIICE i.
.E CA11BRAll0N TESI ILST LOGIC IEST TEST TEST 15 REQUINES <
. IUNC110NAL 11 Nil CIR CK
- 3. Centaisunent' Isolation
- m. :(Continued)
- 2) Automatic Actua- N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 .
' tion logic and Actuation Relays
- 3) Safety Injection See item 1. above for all Safety injection Surveills Requirements.
' w
] '4. Steam Line isolation Manual Initiation M.A. N.A. N.A. R N.A. M.A. .M.A. 1, 2.-3
- y a.
i- A b. Automatic Actuation N.A. M.A N.A N.A. M(1) M(1) 4. 1, 2, 3 h Logic' aml Actuation - Relays
*o c. Contaisument 5 R: ft-Q N.A. N.A. M.A. N.A. 1, 2, 3 l
-Pressure-liigh-High j N.A. M.A.
- d. Steam Line S 'R
-M-d' N.A. M.A. 1, 2, 3 [
Pressure-Low 3 Steam tine Pressure-'S R -M-R N. A.- N.A. M.A. M.A. 3 [ 3 . e. t Negative Rate-liisp fH$ .,
'5. Feedwater Isolation N.A. .N.A. M(1) -M(1) Q 1, z
- a. ' Automatic Actuation M.A. N.A.
logic and Actuation nm.
. 2< ' ,>< .
. Relays .
' l. :.~ ~&'
~
i
, _ . . . , e.-. ++ , _. . ~. - ., , , , .__._____._..._.__a_. - _ . _ . - - _ _ _ _ _ . _ _ _ _ _ . . . _ _ . _ . . - - _ _ _ . _ _ _ _
O inBLE 4.3-2 (Continued) . O ENGINEERED SATETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLAEE REQUIREMEliTS , E m 2- IRIP ANALOG ACTUATING MODES
, c.
CilANNEL DEVICE MASTER SLAVE FOR MIICII j's RELAY SURVEILLANCE OPERATIONAL OPERATIONAL ACTUATION RELAY
$ CHANNEL CilANNEL. CHANNEL CALIBRATION TEST TEST LOGIC TEST TEST TEST 15 REQUIRED FUNCTIONAL UNIT CilECK e
w 5. Feedwater Isolation (Continued) N.A. N.A. N.A. H.A. 1, 2 [
- b. Steam Generator 5 R -M-Q Water Level-High- .
High (P-14)
- c. T avg-Low (P-4 ,
N.A. ' N. A. N.A. N.A. 1, 2 l Interlock) 5 R -M - Q
- d. Doghouse Water N.A. N.A. N.A. 1, 2 l
.R Level-High H.A. H.A. N.A. R(4-)-
a>
- e. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
w i
- 6. Turbine Trip H.A. N.A. R ff. A. N.A. N.A. 1, 2
- a. Manual Initiation M.A.
N.A. M(1) M(1) Q 1, 2
- b. Automatic N.A. N.A. N.A.
Actuation Logic and Actuation Relays gg N.A. N.A. N.A. N.A. 1, 2 l 3@ c. Steam Generator 5 R -M-Q
@@ Water Level-liigh-High 3$ (P-14) ee H.A. R{4)- N.A. N.A. N.A. 1, 2 l
- d. Trip of All Nain N.A. N.A.
- zz PP Feedwater Pumps N.A. R(4)-- N.A. N.A. N.A. 1, 2, 3 l
- e. Reactor Trip (P-4) N.A. H.A.
Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements. 11 r ,+ f. OU 7. Containment' Pressure Control System ' H N.A. N.A. N.A. N.A. 1, 2, 3, 4
- a. Start Permissive 5 R M N.A. N.A N.A. N." 1, 7, 3, 4
- h. Tereination 5 R
TABLE 4.3-2 (Continued) - o ENGINEERED SAFETY FEATURES ACTUA110N SYSTEM INSTRUMENTATION 5tiREllINICE REQUIREMEN15 D
$ ~
IRIP (
.c ANALOG CilANNE L ACTUATING DEVICE MODES MASTER SLAVE FOR WillCll REtAY REtAY SURVEIL [ANCE g CilANNEL CilANNEL OPERAIIONAL OPERATIONAL ACTUATION 1EST 15 REQUIR[D g CHANNEL Cite CK CAtlBP.ATION TEST TESI LOGIC IEST 1EST y FUNCTIONAL UMis e-m
- 8. Auxiliary feedwater N.A. N.A. N.A. 1, 2, 3 N.A. R N.A. N.A.
- a. Manual Initiation 1, 2, 3 N.A. N.A. M(1) M(1) Q N.A. N.A
- b. Automatic Actuation Logic and Actuation
- Relays N.A. N.A N.A I, 2, 3 l Steam Generator 5 R -M-k H.A.
c. t' Water Level-tow-tow Safety Injection See Item 1. above for all Safety injection Surveillance Requirements. d. N.A. R H.A. M(3) N.A. N.A. M.A 1, 2, 3
$ e. Loss-of-Of f site Power N.A. N.A 1, 2 N.A. R N.A.
Trip of All Main N.A. N.A. f. feedwater Pumps o,
- g. Auxiliary Feedwater Suction Pressure- N.A. N.A. N.A. 1, 2, 3 N.A. N.A. N.A. R
.l> > Low y 9. Containment' St.sp l
- Recirculation M(1) Q 1, 2, 3, 4 N.A. N.A. N.A. M(1)
+ a. Automatic Actuation N.A. . .RR togic and Actuation 9 Relays N.A. N.A. 1, 2, 3, 4 M N.A. N.A.
Refueling Water 5 R b.
% Storage Tank level - %' c-low Coincident With $ce Item 1. above, for all Safety Injection Surveillance Requirements.
ip j?, Safety injection w . T
% _ )
TABLE 4.3-2 (Continued) 9 ENGINEERED SAFEIY FEATURES ACTUATION SYSTEM INSTRUMENTATION y SURVEILLANCE REQUIREMENTS TRIP h ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH c-CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE
$ CHANNEL LOGIC TEST TEST TEST IS REQUIRED TEST d FUNCTIONAL UNIT CHECK CALIBRATION TEST w
- p. 10. Loss of Power .
" 4 kV Bus N.A. N.A. M (2) N.A. N.A. N.A. 1, 2, 3, 4
- a. R Undervoltage-Loss of Voltage
' I l b. 4 kV Bus N.A. R N.A. M (2) N.A. N.A. 1, 2, 3, 4 Undervoltage-Grid -
Degraded Voltage w 11. Control Room Area Ventilation Operation
- a. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q All D
w logic and Actuation i Relays u N.A. N.A.
- b. Loss-of-Of fsite N.A. R N.A. R N.A. 1, 2, 3 Power
- c. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
- 12. Containment Air Return
}b and Hydrogen Skimmer } J, Operation N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4 To k a. Manual Initiation N.A.
3 3 N.A. N.A. H.A. M(1) M(1) Q 1, 2, 3, 4 yy b. Automatic N.A.
+ -t Actuation Logic and Rg Actuation Relays O
N.A. N.A. N.A. N.A. 1, 2, 3 l
- -C
- c. Containment 5 R -ft-Q m Pressure-High-High C C
- 13. Annulus Ventilation '
42i~ Operation bU a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 2, 4 r
O I AB1E 4. 3-2 (Continued) n INGINIIRf D sal [iY f[41UR[5 ACIUA110N SYSIEM INSIRUMIN!All0N SURVIT tANCf R[QUIRIM[NIS IRIP N0005 h ACIUAllNG
$ ANALOG DEVICE MA51LR 51 AVE 10R WtilCil CilANNIL EllAY R((AY $URVEILLANCL 7 OPERA 110HAL OPERAIIONAI. ACIUATION i[Si 15 REQtilRID c CilANNEL CilANN[L 1EST tOGIC if5i IIST CllANNEL CALIBRATION TEST $ Cil[CK g IUNCil0NAL UNIT _
e 1, 2, 3, 4
, 13. Annulus Ventilation N.A. M(1) M(1) Q Operation (Continued)^
N.A. M.A. N.A. m
- b. Automatic Actuation logic and Actuation Relays see Ites 1. above f or all Safety injection Surveillance Requirements.
- c. Safety injection N.A. N.A. 1, 2, 3, 4
- 14. Nuclear Service Water Operation R N.A.
, N.A. N.A. 1, 2, 3, 4 N.A. M(1) Q A a. Manual Initiation N.A. N.A. H(1)
M.A. M.A.
- b. Automatic 1co Actuation Logic and Actuation dh Relays M(3) N.A. N.A. 1, 2, :
R N.A. N.A. ' EO H.A.
- c. Loss-of-Offsite N j Power See Item 2. above for all Containment spray Surveillance Requirements. k
- d. Containment Spray Isolation Surveillance Requirements. 4
(( See Item 3.b. above for all Phase "B"
- e. Phase "B" Isolation SeeItes1.aboveforallSafetyInjectionSurveilladeRequirements.
gg f f. Safety Injection N.A. N.A. N.A. 1, 2, 3, 4
- g. Suction Transfer- R(5) N.A. l xx S(5) R(S)
?? Low Pit level e~ w
* 15. Emergency Diesel Generator Operation gg (Diesel Building 33
** Ventilation Operation, w Nuclear Service Water .
N.A. N.A. 1, 2, 3, 4
~
Operation)
- 1 R N.A N.A. N A.
- a. Manu.nl luitiation
_- N
p - TABLE 4.3-2 (Continued) k> ENGINEERED SAFETY FEATURIS ACTUATION SYSIEM INSTRUMENTATION SURVEILLANCE REQUIREHDITS f5. TRIP
- ANALOG AC1UAIING
~
MODES DEVICE MASTER SLAVE FOR MtICH g CilANNEL RELAY RELAY SURVEILLANCE CilANNEL CllANNEL CilANNEL OPERATIONAL OPERAT10NAL AC1UATION Q TEST LOGIC TEST TEST TEST 15 REQUIRED
- FUNCTIONAL UNIT Clif CK CALIBRATION TEST w
** 15. Emergency Diesel
" Generator Operation (Diesel Building Ventilation Operation Nuclear Service Water Operation) (Continued) f N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4
- b. Automatic N.A.
Actuation Logic.
- l. !:' and Actuation
'* Relays u N.A. N.A. N.A. 1, 2, 3, 4
- c. Loss-of-Of f site N.A. R N.A. M(Ts i
- Power o, d. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
- 16. Auxiliary Building Filtered Exhaust Operation N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4
- a. Manual Initiation N.A.
- b. Automatic H.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 Actuation Logic .
and Actuation lelays
~
yg See Ites. 1. above for all Safety Injection Surveillance Requirements. L F n
- c. Safety Injection '
S5 1 1 &b'n , 1 M
o TABLE 4.3-2 (Continued) , n ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRIMENTATION 3 SURVEILLANCE REQUIREMENTS g TRIP g ANALOG ACTUATING MODES .
, CHANNEL DEVICE MASTER SLAVE FOR WHICH c CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE z FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED a
m 17. Diesel Building H Ventilation Operation e-m a. Manual Initiation N. A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4 -
- b. Automatic N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 Actuation Logic -
and Actuation Relays
- c. Emergency Diesel See Item 15. above for all Emergency Diesel Generator Operation Surveillance m Generator Operation Requirements.
s
- 18. Engineered Safety Features -
w Actuation System Interlocks u, o a. Pressurizer N.A. R -M- R N.A. N.A. h.A. N.A. 1, 2, 3 l Pressure P-11
- b. Pressurizer. N.A. R -M- R N.A. N.A. N.A. N.A 1,2,3 1 Pressure, not'P-11
. c. Low-Low Tavg, P-12 N.A. R -M- R N.A. N.A. N.A. N.A. 1, 2, .3 l .w gg d. Reactor Trip, P-4 N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3 hh e. Steam Generator Water Level,-P-14 S R -M-Q N.A. M(1) M(1) Q 1,2,3 l gg
(( - TABLE NOTATIONS PP (1) Each train shall be tested at least every 62 days'on a STAGGERED TEST BASIS. (2) Monthly testing shall consist of voltage sensor relay testing excluding _ actuation of load shedding diesel start, and time - delay timers. ,' gg (3) Monthly testing shall consist of relay testing excluding final actuation of the pumps or valves. (4)g Tt h ,ur;; ilk .cc c.cd .. t Lm ps. f o. d e.. U..i t 2 ...t;l p.-iei te ...tc. ;.4 ST O M u.- = ! STA"^07 g; DelettE. ' .: Oppli:2512) fci h ir.;; thc Or.it 2 first rcfuc?;rs. vu (5) Surveillance Requirements must be met on common (shared) portions of the Nuclear Service Water System C
'when either unit is in MODE 1, 2,-3, or 4. Surveillance Requirements enst be met on unit-specific portions of the Nuclear Service Water System only when the unit is in M00E 1, 2, 3, or a.
t c _ , _ _
3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensures that: (1) the associated ACTION and/or Reactor trip will be inithted when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out-of-service for testing and maintenance, consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features instrumentation and (3) sufficient system functional capability is available f 'a diverse parameters. The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses. The Surveillance Requirements speci-fied for these systems ensure that the overall system functional capability is maintained comparable to .the original desig, standards. The periodic surveil-lance tests performed at the minimum frequencies are sufficient to demonstrate this capability. . Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Sur-veillance Frequencies and Out of Service Times for the Reactor Protection-In-strumentation System " and supplements to that report. - Surveillance intervals andoutof'servicetImesweredeterminedbasedonmaintaininganappropriate level of reliability of the Reactor Protection System and Engineered Safet Features instrumentation.g fImp k .:ntatien-ef-ge:rterly terAdeg-of--RTS h {.e kg pectpened unt44-af ter apprev:1 ef : 511:r teethg-inteeval-fer ESFAS). The ( E 0 Sefsty Eva hath n R: pert- b r WOAP-1 M71 e:: provided 'a e letter dated i Tebreery 21,1^05 fica 0. O. Thsass (N"C) to J. J. Sheppard (WOO-CPab)- WTCAT- P> The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-4 are the nominal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy. To accomodate the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated. Allowable Values for the Setpoints have been specified in Table 3.3-4. 0) era-tion with Setpoints less conservative than the Trip Setpoint but within t1e Allowable Value is acceptable since an allcwance has been made in the safety 4 analysis to accommodate this error. 3 4 CATAWBA - UNITS 1 & 2 B 3/4 3-1 Amendment No.1 (Unit 1) I Amendment No. (Unit 2)
i . . INJ6KT" b for faje. 6 3l4 3 ~l Tho WAC Sct(e*kt EwlaaOn Refor1T Ar -dn wcAf- toxnl sala mtwM is leka W Mra ry at, tw +nm
- c. c. rben 4 (vAc) b r.7. 5kpAe2 (wos), Ptfrary u., fff?
sw c. e. Ron ; Ga.c) % x.n. wew% (wos), anR ara I so, its w e . r. non *, cuac) n a . r. ca c , ,;, (woc). r m 1 % e m c+r, i aEE % al cooRhbn.r ate ccg i n.k B .tuptwf tie WCAf, ion ( Alnj : (s) common c ause- eva \va$on -for 6 .lvre i, -tk cAcnnel.r ebay0
-to de q varkcly +wl- fa mey a a9 alh'w( +erHny {oeeLidle '
c masa cavie. -f,n(vas , (2. inrMitD Gran catalk pc tubig in de bypn mee., anA. (1) pe d u lo w h e Aeon ens +<d'n, 1 approprick sljas%1:c -(se 'i ntframed .se-1f,n+ meL0olop % / a(bet A Sc'ef+ an+kiexte as a. .,sa (+ d ~ len Rep + rarvel ikw. i
% I NO Cl(AvCJG l T I M (A C. E l INSTRUMENTATION _,
BASES REACTOR Trip SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM TT(5Th0 MENTATION (Continued) The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels. Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties. Sensor and rack instrumentation utilized in these channels are expected to be capable of Operating within the allowances of these uncertainty magnitudes. Rack drift i in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance. Being that there is a small statistical chance that this will happen, an infrequent excessive drift is expected. Rack or sensor drift, in excess of the allows ce that is more than occasional, may be indicative of more serious problems and should warrant further investigation. The measuremer. of respon:e time at the specified frequencies provider, assurance that the Reactor trip and the Engineered Safety Features actuation associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable. Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either: (1) in place, onsite, or offsite test measurements, or (2) utilizing replacement sensors with certified response time. The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded. If they are, the signals are combined into logic matrices sensitive to combina-tions indicative of various accidents, events, and transients. Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident: (1) Safety Injection pumps start and automatic valves position, (2) Reactor trip, (3) feed-water isolation, (4) startup of the emergency diesel generators, (5) containment 4 CATAWBA - UNITS 1 & 2 B 3/4 3-2 Amendment No.101(Unit 1) Amendment No. 95(Unit 2)
o, , No CAWWS Wti f/l M . INSTRUMENTATION BASES REACTOR TRIP $YSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine trip (9) auxiliary feedwater pumps start and automatic valves position, (10) nuclear service water pumps start and automatic valves position, and (11) component cooling pumps start and automatic valves position. The Engineered Safety Features Actuation System interlocks perform the following functions: P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater vt ves on T 3yg below Setpoint, prevents the opening of the main feedwater valves which were closed by a Safety injection or High Steam Generator Water tevel signal, allows safety injection block 50 that components can be reset or tripped. Reactor not tripped prevents manual Diock of Safety injection. P-11 Defeats the manual block of Safety injection actuation on low pres-surizer pressure and low steam line pressure and defeats steam line isolation on negative steam line pressure rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level. P-12 On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump block for the cooldown valves only. On increasing reactor coolant loop temper-ature, P-12 automatically defeats the manual bypass of the steam dumo
; block.
P-14 On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, pumps and turbine and inhibits fsedwater control valve modulation. Surveillances for the Reactor Trip Bypass Breakers are included in response to the NRC's Generic Letter 85-09, dated May 23, 1985. 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that: (1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof rea?.hes its Setpoint,-(2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance. Th* radiation monitors for plant operations senses radiation levels in selected plant systems ana locations and determines whether or not predetermined limits are being exceeded. If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems. CATAWBA - UNITS 1 & 2 B 3/4 3-3 Amendment No.63 (Unit 1) 1 Amendment No.57 (Unit 2) to
. - - _ ___ - ._ _ _ _ _ _ _ _ _ - - - _}}