ML20065E603
| ML20065E603 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/20/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065E613 | List: |
| References | |
| NUDOCS 9010020236 | |
| Download: ML20065E603 (22) | |
Text
o kS 980g e
o UNITED STATES
+"
l[i I,g _
NUutE AR REGULATORY COMMISSION
.r
. t WASHINGTON, D. C. 205$$ ~
k...../
UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET N0. STN 50-483 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 57 License No NPF-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by Union Electric Company (UE,thelicensee)datedApril 12, 1990 as supplemented by letter dated July 7, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations cet forth in 10 CFR Chapter-1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by
@Mi this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted g.
in compliance with the Comission's regulations;
)4 D.
The issuance of this amendment will not be inimical to the common i
defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51-of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended.by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
9010020236 900920
{DR ADOCK 05000483 F'DC 4
u..
2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A,'as revised through Amendment No. 57, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are-hereby incorporated into the license.
UE shall operate the facility in accordance with the Technical Specifications and:the Environmental Protection Plan.
3.
This license amendment is effective immediately to be implemented upon startup from the 1990 refueling outage.
The. licensee has agreed to immediately inform the Commission, in writing, of the implementation date.
FOR THE NUCLEAR REGULATORY COMMISSION Atti
.w
/
John N. Hannon, Director Project Directorate 111-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation-
Attachment:
Changes to the; Technical Specifications Date'of issuance:
September 20, 1990 5
e
s ATTACHMENT-TO LICENSE AMENDMENT NO. 57 OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified i
below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Corresponding overleaf pages are provided to maintain document completeness.
REMOVE INSERT 2-4 2-4 2-5 2-5 2-5a 2-5a 2-1 2-7 2-9 2-9 2 2-10 B 2-5 B 2-5 3/4 3-9 3/4 3-9 3/4 3-12a 3/4 3-12a 3/4 3-25(a) 3/4 3-25(a) 3/4-3-25(b) 3/43-25(b) 3/43-25(d) 3/4 3-25(d) 3/43-25(e) 3/4 3-25(e)
5;,"'
gq L-SIFETY ' LIMITS AND LIMITING SAFFTY-SYSTEM SETTINGS.
2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS
- 2. 2.'l The Reactor Trip System Instrumentation and Interlocks Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY:
As shown for each channel in Table 3.3-1.
ACTION:
a.
With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent ith the Trip Setpoint value.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R.+ S 5, TA Where:
Z=
The value from Column Z of Table 2.2-l'for the affected channel, R=
The "as measured" value (in percent span) of rack error for the affected channel, S=
Either the "as measured" value (in percent' span) of the sensor error, or the value from Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value' from Column TA (Total Allowance) of Table 2.2-1 for the affected channel.
CALLAWAY - UNIT 1 2-3 I
'gr.
i TABLE 2.2-1 REACTOR' TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 1
n TOTAL SENSOR ERROR E
FUNCTIONAL UNIT
' ALLOWANCE (TA)
Z_
M TRIP SETPOINT ALLOWABLE VALUE' x5
.l.
Manual Reactor Trip.
N;A.
N.A.
N.A.
N.A.
N.A.
2.
Power Range, Neutron Flux E
a.
High Setpoint
- 7. 5 4.56 0
<109% of RTP*
<112.3% of RTP*
]
b.' Low Setpoint 8.3 4.56 0
<25% of RTP*
<28.3% of RTP*
3.
Power Range, Neutron Flux, 2.4 0.5 0
<4% of RTP* with 16.3% of RTP* with High Positive Rate a time constant a time constant-
>2 seconds
>2 seconds 4.
Deleted 5.
Intermediate Range, 17.0 8.41 0'
<25% of RTP*
<35.3% of RTP*
Neutron Flux p
6.
Source Range, Neutron Flux 17.0 10.01 0 1105 1
5 1 6 x 10 cps cps 7.
Overtemperature AT 9.3 6.47 1.83 See Note 1 See Note 2
+1.24***
8.
Overpower AT 5.7 1.90 1.65 See Note 3 See Note 4 9.
Pressurizer Pressure-Low 5.0 2.21 2.0
>1885 psig
>1874 psig 10.
Pressurizer Pressure-High 7.5 4.96 1.0 12385 psig 12400 psig g
8 11.
Pressurizer Water Level-8.0 2.18 2.0 j
g High
-<92% of instrument
<93.8% of instrument i
span span i
=
l 12.
Reactor Coolant Flow-Low 2.5 1.38 0.6
>90% of loop
>88.8% of loop l
E minimum measured minimum measured.
l flow **
flow **
5 g
- RTP = RATED THERMAL POWER 3
- Minimum Measured Flow = 95,660 gpm P
- Two Allowances (temperature and. pressure, respectively) u, me 4
-7.-.,
..c--%-
c
_y, w--.
err-- -.
p
TABLE 2.2-1 (Continued) 53 ~
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS l-
. ?!
-SENSOR D
TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA)
Z (S)
TRIP SETPOINT
' ALLOWABLE VALUE C
55 13.
Steam Generator Water
))-
Level Low-Low a.
Vessel AT Equivalent 6.0 2.72
.1 65 5 Vessel AT
- 5. Vessel AT 5.10% RTP Equivalent to Equivalent to Vessel aT (Power 1)-
10% RTP 13.9% RTP Coincident with-Steam Generator Water 20.2 17.58 2.0
> 20.2% of Narrow
> 18.4% of Narrow Level Low-Low (Adverse Range Instrument Range Instrument n3 di Containment Environment)
Span Span and Centainment Pressure -
2.8 0.71 2.0
$_l.5 psig
$_2.0 psig Environmental Allowance Modifier F
OR S-Steam Generator Water 14.8 12.18 2.0
> 14.8% of Narrow
> 13.0% of Narrow Level Low-Low (Normal Range Instrument Range Instrument Containment Environment)
Span Span 5
With a Time Delay, (t)
< 232 seconds
< 240 seconds 3:
m.
M 4
TABLE 2.2-1 (Continued)-
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 25 SENSOR
' TOTAL ERROR FUNCTIONAL UNIT
-ALLOWANCE (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE-E Z
' 13.
Steam Generator Water Level Low-Low (Continued) m b.
10% RTP < Vessel AT 6.0 2.72 1.65
< Vessel AT'
< Vessel AT Equivalent < 20% RTP Equivalent to Equivalent to Vesse!:AT-(Power 2) 20% RTP 23.9% RTP Coincident with Steam Generator Water 20.2 17.58
- 2. 0
> 20.2% of Narrow
> 18.4% of Narrow.
m 5,
Level Low-Low (Adverse fange Instrument Range Instrument
{
Containment Environment)
Span Span and Containment Pressure-2.8 0.71 2.0
< l.5 psig
-< 2.0 psig Environmental Allowance Modifier OR Steam Generator Water 14.8 12.18 2.0
> 14.8% of Narrow
> 13.0% of Narrow Level Low-Low (Normal Fange Instrument Range' Instrument Containment Environment)
Span Span Q
'With a Time Delay, (t)
< 122 second's
< 130 seconds 0
e 4&
..-l.--
m..s u-_.
-mm.
.-_,ve.
~=-----m----
_wm_
'ms
.-m_-
._,-..___h._.s
^
' jtp -
g ;;{
u
- Y s..
TA8LE 2.2-1 (Contine=d) 9 TA8thNOTATIONS
~
r-NOTE 1: OVERTEMPERATURE'AT
)
' )[
(3f,sgi $ AT, { K, - K D (1, y,3) - T'] + K (P - P') - f (al)].
AT 2
3
+g, z
w Where:
AT Measured AT I
=
l I{
= LLead-lag compensator on measured AT; Time constants utilized in lead-lag compensator for AT, 1
=8s, In Y2
=
Y2 = 3 5; 1
g,,,3 Lag compensator on measured AT;
=
Time constant utilized in the lag compensator for AT, Ta = 0 s; 13
=
' Indicated AT at RATED THERMAL POWER:
AT,
=
j K
1.15;
=
K
=
2
' O.0251/*F; I * S E
I * '55 The function generated by the lead-lag compensator for T
=
dynamic compensation;-
8'9 5
A Time constants utilized in the lead-lag compensator for T,,g, t = 28 s, r.,
is
=
rs = 4 s;
=
T Average' temperature, *F;
=
g
'i I
,5
.g,
3 Lag compensator on' measured T,,g;
=
O i
Time constant utilized in the measured T, lag compensator, is = 0 s; is
=
L L
y
- ~L'
~
.y
=p
~
~
N
- c _
u
= 2:~
~
TABLE 2.2-1 (Continued) e hb TABLE NOTATIONS (Continued)
R
$i N0il 1: (Continued)
T'
< 588.4*F (Referenced T,yg _at RATED THERMAL POWER);
l 2
21 K3
= 0.00116; m
' Pressurizer pressure, psig; P
=
2235 psig (Nominal RCS operating pressure);
P'
=
Laplace transform operator, s 1; 5
=
and f (al) is a function of-the indicated difference between top and bottom detectors of the t
power-range neutron ion chambers; with gains to be selected based on measured instrument
}
response during plant STARTUP tests such that:
- 9 between -35% and + 6%, f (AI) = 0, where qt and q are percent rtATED THERMAL l
(i) For qt i
q b
is total THERMAL POWER in the top and bottom halves of the core respectively, and qt+9b POWER in percent of RATED THERMAL POWER; l
exceeds -35%, the AT Trip Setpoint shall (ii) For each percent that the magnitude of qt -9b be automatically reduced by 1.91% of its value at RATED THERMAL POWER; and l
iL exceeds +6%, the aT Trip Setpoint shall
)
(iii) For each percent that the magnitude of q -9b t
be automatically reduced by 1.89% of its value at RATED THERMAL POWER.
l 5
~
s:
NOTE 2: The channel's maximum. Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3%.
i.
of AT span.
. ?*
b; W
O
?
.N TABLE 2.2-1 (Continued) h TABLENDTkTIONS(Continued).
E E
NOTE 3:
OVERPOWER AT AT (1 + 1 5) $ AT, M. - Ks IY T - 4 [T (3
, 3) - T9 - f (al)l '
I 1
2 1
t 5 1
1.5 3
s Measured AT; l
Idhere-AT
=
1 1
Lead-lag compensator on measured AT;
=
Time constants utilized in lead-lag compensator for AT,
=
It. T2 ti, = 8 s., T2 = 3 Si 1
L89 Co8Pensator on measu M AT;.
=
1+153 mO Time constant utilized in the lag compensator for AT, 13 = 0 s;
=
T3 Indicated AT at RATED THERMAL POWER; AT,
=
1.000; K.
=
T 0.02/*F for increasing average temperature and 0 for decreasing average g
Ks
=
g-temperature; m
S j'
The function generated by the rate-lag compensator for T,,, dynamic
=
g 3
compensation; 2
Time constant utilized in the rate 'ig compensator for T,,,,
ty = 10 s;
=
17 g
l + 1.5 Lag c e nsator on measu M T,,g;
=
Time constant utilized in the measured T,,g lag compensator, rs = 0 s;.
=
ts-
- - _ ~ -
w--
--1--
- - ~ - - -
u
,, u,
a
?
TABLE 2.2-1 (Continued)
- \\
l}
TABLE NOTATIONS (Continued) r-EE.
NOTE 3:
(Continued)
E 0.0065/ F for T > T" and Kg = 0 for T 1 T";
Kg
=
C
^
Average Temperature, F;.
55 T
=
-4 Indicated T,yg at RATED THERMAL POWER (Calibration temperature for AT
~'
T"
=
instrumentation, 1 588.4 F);
Laplace transform operator, s 1; and 5
=
f (aI) 0 for all al.
=
2 NOTE 4: The channel's maximum Trip Setpoint shall not exceed 'ts computed Trip Setpoint by more than -
}',
3.0% of AT span.
g O
st R
a H
- E l
b I
3B
l c :l q
MMITINGSAFETYSYSTEMSETTINGS e
BASES Intemediate and Source Range, Neutron Flux The Intermediate and Source Range, Neutron fiux trips provide core protec-tion during reactor startup to mitigate the consequences of an uncontrolled rod cluster contrul assembly bank withdrawal from a subcritical condition. These trips, provide redundant protection to the Low Setpoint trip of the Power Range, I
Neutron Flux channels.
The Source Range channels will initiate a Reactor trip at about 105 counts per second unless manually blocked when P-6 becomes active.
The Intermediate Range channels will initiate a Reactor trip at a current level equivalent to approximately 25% of RATED THERMAL POWER unless manually blocked when P-10'becomes active.
Overtemperature AT The Overtemperature AT trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribu-tion, provided that the transient is slow with respect to piping transit delays from the core to the temperature detectors, and pressure is within the range I
between the Pressurizer High and Low Pressure trips.
The Setpoint is automat-ically varied with:
(1) coolant temperature to correct for temperature induced changes in density and heat capacity of water and includes dynamic compensation for piping delays from the core to the loop temperature detectors, (2) pressurizer pressure, and (3) axial power distribution. With nonnal axial power distribution, this Reactor trip limit is always below the core Safety Limit as shown in Figure 2.1-1.
If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detec-tors, the Reactor trip is automatically reduced according to the notations in Table 2.2-1.
Delta-To, as used in the Overtemperature and Overpower AT trips, represents the 100% RTP value as measured by the plant for each loop. _ This nonnalizes each loop's AT trips to the actual operating conditions existing at the time of measurement thus forcing the trip to reflect the equivalent full power condi-tions-as assumed in the accident analyses.
These differences in vessel aT can arise due to several factors, the most prevalent being measured RCS loop flows greater than Minimum Measured Flow, and slightly asynnetric power distributions between quadrants.
While RCS loop flows are not expected to change with cycle life, radial power redistribution between quadrants may occur, resulting in small changes in loop specific vessel aT values. Accurate determination of the loop specific vessel AT value should be made when performin quarterly recalibration and.under steady state conditions (g the Incore/Excore i.e., power distribu-tions not affected by Xe or other transient conditions).
Overpower 4T-The Overpower aT trip provides assurance of fuel integrity (e.g., no fuel pellet melting and less than 1% cladding strain) under all possible overpower conditions, limits the required range for Overtemperature AT trip, and provides CALLAWAY - UNIT 1 B 2-5 Amendment No, M,57
G
\\
+
3 LIMITING SAFETY SYSTEM SETTINGS BASES Overpower AT (Continued) a backup to the High Neutron Flux trip.
The Setpoint is automatically varied with:
(1) coolant temperature to correct for temperature induced changes in density and heat capacity of water, and (2) rate of change of temperature' for -
dynamic compensation for piping delays from the core to the loop temperature detectors, to ensure-that the _ allowable heat generation rate (kW/ft) is not exceeded. The-0verpower AT trip provides protection to mitigate the conse-quences_of various size steam breaks as reported in WCAP-9226, " Reactor Core Response to Excessive Secondary Steam Releases."
Delta-T, as used in the Overtemperature and Overpower AT trips, represents o
the 100% RTP value as measured by the plant for each loop.
This normalizes each loop's AT trips to the actual operating conditions existing at the time of measurement, thus forcing th? trip to reflect the equivalent full power condi-tions as assumed in the accident analyses.
These differences in vessel AT can
~
arise due to several factors, the most prevalent being measured RCS loop flows greater than Minimum Measured Flow, and slightly asymmetric power distributions between quadrants. While RCS loop flows are not expected to change with cycle life, radial. power redistribution between quadrants may occur, resulting in small changes fin loop specific vessel AT values. Accurate determination of the loop specific vessel aT value should be made when performin quarterly recalibration and under steady state conditions (g the Incore/Excore i.e., power'distri-buti_ons' not affected by Xe or other transient conditions).
Pressurizer Pressure In each of the pressurizer pressure channels, there are two independent bistables, each with its own Trip Setting to provide for a High and Low Pressure trip thus limiting the pressure range in which reactor operation is permitted. The Low Setpoint trip protects against low pressure which could lead to DNB by tripping the reactor in the event of a loss of reactor coolant l_
pressure.
On decreasing power-the Low Setpoint trip is automatically blocked by P-7 (a power level of approximately 10% of RATED THERMAL POWER with turbine impulse chamber pressure at approximately 10% of full power equivalent); and on increasing power, automatically reinstated by P-7, 1
The High Setpoint trip functions in conjunction with the pressurizer relief and safety vahes to protect the Reactor Coolant System against system overpressure.
Pressurizer Water Level The Pressurizer High Water Level trip is provided to prevent i ter relief through the pressurizer safety valves. On decreasing power the Pr.surizer High Water Level trip is-automatically blocked by P-7 (a power level of CALLAWAY - UNIT 1 B 2-6 Amendment No.
28
.,[
TABLE 4.3-1 o.
~@
REACTOR TRIP SYSTEN INSTRUE NTATION SURVEILLANCE REQUIRENENTS I
~
-g.
I TRIP ANALOG ACTUATING N00ES FOR CHANNEL DEVICE WHICM E
CMANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE Z
FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST-15 REQUIRED w
1.
Manual Reactor Trip w.A.
N.A.
~*, N.A.
R(16)
N.A.
1, 2, 3*,
4*, 5 '
2.
Power Range, Neutron Flux-a.
High Setpoint S
D(2,4),
Q(14)
N.A.
N.A.
1, 2 N(3, 4) -
l Q(4,6),
R(4 5)-
i b.
Low Setpoint 5
R(4)
S/U(1)
N.A.
N.A.
IM,2 i
i R
3..
Power Range, Neutron Flux, M.A.
R(4)
Q(14)
N.A.
N.A.
1, 2 High Positive Rate T
4.
Deleted l
l l
S.
Intermediate Range, S
R(4,5)
S/U(1)
N.A.
N.A.
~IM,2 i
Neutron Flux g
e l
6.
Source Range, Neutron Flux S
R(4,5,12)
S/U(1),Q(9,14)
N.A.
N.A.
2N, 3, 4, 5 m
5 7.
Overteeperature AT S
R Q(14)
N.A.
M.A.
1, 2
'l z
P 8.
Overpower AT S
R Q(14)
N.A.
N.A.
1, 2 j
9.
Pressurizer Pressure-Low 5
R Q(14)
N.A.
M.A.
1 10.
Pressurizer Pressure-High 5
R Q(14)
N.A.
N.A.
1, 2 -
l mw 11.
Pressurizer Water Level-High S
R Q(14)
N.A.
N.A.
1 l
12.
Reactor Coolant Flow-Low S
R Q(14)
M.A.
M.A.
1 b
=
=
=
TABLE 4.3-1'(Continued) g
-. REACTOR TRIP SYSTEM INSTRUMENTATION' SURVEILLANCE REQUIREMENTS l-p-TRIP 3
ANALOG ACTUATING MODES CHANNEL DEVICE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE' c
FUNCTIONAL UNIT _
C11ECK
' CALIBRATION TEST TEST LOGIC TEST IS' REQUIRED z
13.
Steam Generator Water Level Low-Low a.
Steam: Generator Water S
R
- Q (14,15)
N.A.
N.A.
1, 2 Level Low-Low (Adverse Containment Environment) b.
Steam Generator Water S
R Q (14,15)
N.A.
N.A.
1,. 2.
m1 Level Low-Low (Normal'
' Containment Environment)
U c.
Vessel AT (Power-1, S
R Q (14,15)
N.A.
N.A.
1, 2 Power-2) d.
Containment Pressure-S R
Q (14,15)
N.A.
N.A.
1, ' 2 Environmental Allowance-Modifier k
- 14. Undervoltage - Reactor N.A.
' R N.A.
Q (14,15)
N.A.
1 Coolant Pumps
=
'd k
15.
Underfrequency - Reactor N.A.
R N.A.
Q (14)
N.A.
1 Coolant Purpps t
2
?
- 16. Turbine Trip y."g a.
Low-Fluid Oil Pressure N.A.
R N.A.
S/U (1,10)
N.A.
I b.
Turbine Stop iMlve N.A.
R N.A.
S/U (1,10)
N.A.
1 Closure h
)
b.
,w.
9..
e.-
y
_Nm
-wgy..
es-
...m.
r'*
Wm'9-4* =
- rmk
- a
TABLE 4.3-1 (Continued)
TABLE NOTATIONS (10) Setpoint-verification is not required.
~
'(11) Following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verifi-cation of the Undervoltage and Shunt trips.
(12) At least once per 18 months during s.htdown, verify that on a simulated Boron Dilution Doubling test signal the normal CVCS discharge valves will close and the centrifugal charging pumps suction valves from the RWST will open within 30 seconds.
(13) Deleted l
(14)' Each channel shal_1 be tested at least every 92 days on a STAGGERED TEST BASIS.
(15) The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.
(16) 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 OPERABILITY of the Bypass Breaker trip circuit.
.(17). Local manual shunt trip prior to placing breaker in service.
(18) Automatic Undervoltage Trip.
5 CALLAWAY - UNIT 1 3/4 3-12a Amendment No. JP,/24,/3#, 57 a'
3
~
~
i TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRtNENTATION TRIP SETPCINTS 4
g 3
4 I
TOTAL-SENSOR TRIP
' ALLOWABLE l
[
FUNCTIONAL UNIT ALLOWANCE (TA)
Z_
ERROR (5)- SETM) INT '
VALUE E
5.
Feedwater Isolation (Continued)
.-e b.
Steam Generator Water Level-High-High S.0 2.18 2.0
-< 78K of
~< 79.8K of narrow range narrow range' instressent instrimment span span c.
Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
6.
Manual Initiation N.A.
M.A.
M.A.
N.A.
M.A.
w4 b.
Automatic Actuation i
Logic and Actuation
~
Relays (SSPS)
N.A.
M.A.
M.A.
M.A.
M.A.
c.
Automat 1_c Actuation Logic and Actuation Relays (80P ESFAS)
N.' A.
M.A.
N.A.
N.A.
N.A.
d, Steam Generator Water k
Level-Low-Low a
R a
i t
= -
+
x
/'
' TABLE 3.3-4'(Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
-?
E-SENSOR' 5
. TOTAL ERROR TRIP ALLOWABLE 7
FUNCTIONAL UNIT ALLOWANCE (TA)
Z
'(S)
' SETPOIN_T VALUE T
E 6.
Auxiliary Feedwater (Continued) g
- d. Steam Generator Water Level Low-Low (Continued)
- 1) Start Motor-Driven Pumps
- a. Vessel AT' Equivalent 6.0 2 72 1.65
< Vessel AT
< Vessel AT
< 10%-RTP Equivalent to Equivalent to
{
Tessel AT (Power-1) 10% RTP 13.9% RTP "4
Coincident with h
. Steam Generator. Water 20.2 17.58
- 2. 0
> 20.2% of Narrow -
> 18.4% of Narrow
~
Level Low-Low. (Adverse Range Instrument Range Instrument Containment Environment)
Span Span and-Containment Pressure -
2.8 0.71 2.0
< l.5 psig'
< 2.0.psig 37 Environmental Allowance -
Modifier T
OR Steam Generator Water 14.8 12.18-
- 2. 0
> 14.8% of Narrow
> 13.0% of Narrow Level Low-Low (Nomal lange Instrument lange Instrument ConteinmentEnvironment)
Span Span g
With a Time Delay, (t)
. < 232 seconds
< 240 seconds f
.=
w v.
,---y y
r q m.
c
=-
_..-p y-
~5-g
=_,
~ 3-TABLE 3.3-4 (Continued)
~
y ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS.
~
~
k SENSOR Q
TOTAL ERROR TRIP ALLOWABLE.
FUNCTIONAL UNIT' ALLOWANCE (TA)
Z-(S)
SETPOINT VALUE C5 6.
Auxiliary Feedwater (Continued)
-e
- d. Steam Generator Water Level Low-Low (Continued)
- 1) Start Motor-Driven Pumps (Continued)
- b. 10% RTP < Vessel AT 6.0 2./2 1.65
< Vessel AT
< Vessel AT R
Equivalent < 20% RTP Equivalent to Eauivalent to Vessel AT (Power-2) 20% RTP 23.9% RTP a
Y' N
Coincident. with E
Steam Generatnr Watcr 20.2 17.58 2.0
> 20.2% of Narrow
> 18.4% of Narrow Level i.ow-Low - ( Adverse Range Instrument Range Instrument Containment Environment)
Span Span and
[
Containment Pressure--
2.8 0.71 2.0
< l.5 psig
< 2.0 psig g
Environmental Allowance g
Modifier 5
OR g
Steam Generator Water 14.8 12.18 2.0
> 14.8% of Narrow
> 13.0% of Narrow g
Level Low-Low 'Nomal '
Range Instrument Range Instrument g
Containment Environment)
Span Span With a Time Delay, (t)
< 122 seconds
< 130 seconds 2,-
e.
y~
,:L..
a.
s
~.'
. TABLE 3.3-4 (Continu'ed)'
ENGINEERED SAFETY FEATURESJCTUATION SYSTEM INSTRUMENTATION ' TRIP SETPOINTS 5
SENSOR S
TOTAL-
' ERROR TRIP ALLOWA3LE-
[
FUNCTIONAL UNIT'
' ALLOWANCE (TAl Z
(S)
SETPOINT VALUE E
6.
Auxiliary Feedwater -(Continued)
Q
- d. Steam Generator Water Level Low-Low (Continued)
- 1) Start Motor-Driven Pumps (Continued)
- c. Vessel AT. Equivalent
> 20% RTP g
z.
y Coincident with.
m M
Steam Generator Water -
-20.2 17.58 2.0
> 20.2% of Narrow
> 18.4% of. Narrow.
E Level Low-Low (Adverse Range Instrument-Range' Instrument Containment Environment)
Span Span
-and Containment Pressure -
2.8 0.71 2.0 5 1.5 psig i 2.0 psig Environmental Allowance g
Modifiar g
aj 0R o
=c Steam Generator Water 14.8 12.18
' 2. 0
> 14.8%'of Narrow
> 13.0% of Narrow P
Level Low-Low (Normal O
Containment Environment).
Range Instrument Range Instrument' Span Span r
.e f...
.m'-
-r'-
a,-p W<
,u..
m.
3
'.'%-q-g
'.+yss.
-,-w.
e qp q
.a TABLE 3.3-4 (Continued) o ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IM TRUMENTATION TRIP SETPOINTS V
E SENSOR' S
' TOTAL ERROR TRIP ALLOWABLE
]
FUNCTIONAL UNIT-ALLOWANCE (TA)
'Z (S)
SETPOINT.
VALUE-E 6.
Auxiliary Feedwater (Continued)-'
- d. Steam Generator Water Level Lou-Low (Continued)
- 2) Start: Turbine-Driven Pt;mp
- a. Vessel AT Equivalent 6.0 2.72 1.65
< Vessel AT
< Vessel AT
< 10% RTP Equivalent to Equivalent to Vessel aT (Power-1) 10% RTP 13.9% RTP w
'2:
Coincident with w
42 Steam Generator Water 20.2 17.58 2.0
> 20.2% of Narrow
> 18.4% of Narrow S
. Level Low-Low (Adverse Range Instrument Range Instrument Containment Environment)
Span Span and Containment Pressure -
2.8 0.71
- 2. 0
< l.5 psig
< 2.0 psig Environmental Allowance g
Modifier
.o OR g
Steam Generator Water 14.8 12.18 2.0
> 14.8% of Narrow
> 13.0% of Narrow 2
P Level Low-Low (Nomal Fange Instrument Range Instrument Containment Environment)-
Span Span O
With a Time Delay. (t)
< 232 seconds
< 240 seconds 1
'I
.. _.._ _ _ = _.. _.. _ _
' TABLE 3.3-4 (Continued) g NGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS F
SENSOR S
. TOTAL ERROR TRIP ALLOWABLE
]
FUNCTIONAL UNIT ALLOWANCE (TA)
Z (S)
SETPOINT VALUE E
6.
Auxiliary Feedwater (Continued)
- d. Steam Generator Water Level Low-Low.(Continued)
- 2) Start Turbine-Driven Pump (Continued)
- b. 10% RTP < Vessel AT 6.0 2.72 1.65
< Vessel AT
< Vessel AT Equivalent - 20% RTP-Equivalent to Equivalent to w
1 Vessel cT (Power-2) 20% RTP 23.9% RTP w
k Coincident with Steam Generator Water 20.2 17.58 2.0
> 20.2% of Narrow
> 18.4% of Narrow Level Low-Low (Adverse Range Instrument Range Instrument Containment Environment)
Span Span And g
Containment Pressure -
2.8 0.71 2.0 m
Environmental Allowance
_ < 1.5 psig
< 2.0 psig R
Modifier N
R OR Steam Generator Water.
14.8 12.18 2.0
> 14.8%'of Narrow
> 13.0% of Narrow Q
Level Low-Low (Normal Range Instrument.
Range Instrument Containment Environment) m Span Span o
With a. Time Delay, (t)
< 122 seconds
< 130 seconds e-e,
,w,
..y c
-