ML20069M064
| ML20069M064 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/13/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069M068 | List: |
| References | |
| NUDOCS 9406210103 | |
| Download: ML20069M064 (4) | |
Text
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@$ R TABLE 2.2-1 (Continued) 08 2.0 E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 80 "
no '
NOTATION xu Cz
@f Z NOTE 1: OVERTEMPERATURE AT oo m uSS "
(AT/AT )
(1 + T S) (
1
) s K, - K2 (1 + r,5)[T(
1
)-T '] + K3 (P-P') - f (AI) o 3
3 EP, E 1+7S 1+TS 1 + T'3S 1+7S 2
3 6
,4 1 c' Where:
AT Measured AT by Loop Narrow Range RTD, AT Indicated AT at RATED THERMAL POWER, o
Lead-lag compensator on measured AT, I+TS 3
I+T52 7,
r
- Time constants utilized in the lead-lag controller for 3
2 AT, as presented in the Core Operating Limits Report, l
Lag compensator on measured AT, 1
1+T 3 Time constant utilized in the lag compensator for AT, as presented in the Core 7
3 Operating Limits Report, EE 8@
K Overtemperature AT reactor trip setpoint as presented in the Core Operating 3
Limits Report, 88 K
Overtemperature AT reactor trip heatup setpoint penalty coefficient as presented 2
& K.
in the Core Operating Limits Report, The function generated by the lead-lag controller for T,, dynamic compensation, C"
l + r, S
]
1+TS3 CC Time constants utilized in the lead-lag controller for 1,,, as presented in the L E.
7, r
4 3
Core Operating Limits Report,
$O Average temperature, *F, T
Lag compensator on measured T,,,
1 1+7S6
TABLE 2.2-1 (Continuesl E
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
_o
[
NOTATION (Continued)
NOTE 1:
(Continued)
[
Time constant utilized in the measured T,, lag compensator, as presented in 7
6 the Core Operating Limits Report,
,z
[
T' s 588.2 *F Reference T,y at RATED THERMAL POWER, Overtemperature AT reactor trip depressurization setpoint penalty coefficient as K
3 presented in the Core Operating Limits Report, Pressurizer pressure, psig, P
2235 psig (Nominal RCS operating pressure),
P'
=
Laplace transform operator, sec 1, S
and f (AI) is a function of the indicated difference between top and bottom detectors of the 3
power-range nuclear ion chambers; with gains to be selected based on measured instrument g
response during plant startup tests such that:
SE (i) for q
-q between the " positive" and " negative" f (AI) breakpoints as presented in the 3
Core bpera, ting Limits Report; f (AI) = 0, where q* and q, d q, + q, is total S@
S are percent RATED THERMAL POWER 3
in the top and bottom halves of the core respectively, an in percent of RATED THERMAL POWER; g
(ii) for each percent imbalance that the magnitude of qz - q3, is more negative than the f (AI) 3
" negative" breakpoint presented in the Core Operating Limits Report, the AT Trip Setpoint mw shall be automatically reduced by the f (AI) " negative" slope presented in the Core 3
((
Operating Limits Report; and c+ e (iii) for each percent imbalance that the magnitude of qz - q3, is more positive than the f (AI) m-3
~
" positive" breakpoint presented in the Core Operating Limits Report, the AT Trip Setpoint shall be automatically reduced by the f (A1) " positive" slope presented in the Core 3
Operating Limits Report.
A
xe TABLE 2.2-1 (Continued)
S A
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS h
NOTATION (Continued) 5 As defined in Note 1, T
T
s 588.2 *F Reference T,y at RATED THERMAL POWER, N
As defined in Note 1, and S
f (AI) is a function of the indicated difference between top and bottom detectors of the 2power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) for q
-q between the " positive" and " negative" f (AI) breakpoints as presented in the 2
Core bpera, ting Limits Report; f (AI) - 0, where q, and q, d q, + q3 are percent RATED THERMAL POWER 2
in the top and bottom halves of the core respectively, an is total THERMAL POWER 7
2 in percent of RATED THERMAL POWER; (ii) for each percent imbalance that the magnitude of q, - 4 is more negative than the f (al) 3 2
" negative" breakpoint presented in the Core Operating Limits Report, the oT Trip Setpoint 33gg shall be automatically reduced by the f (al) " negative" slope presented in the Core 2
ELit Operating Limits Report; and 55 gg (iii) for each percent imbalance that the magnitude of q, - q, is more positive than the f (AI) z
" positive" breakpoint presented in the Core Operating Limits Report, the oT Trip Setpoint 2zPP shall be automatically reduced by the f (AI) " positive" slope presented in the Core 2
Operating Limits Report.
DlO
![5[
Note 3:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 4.4% of Rated Thermal Power.
ES21 The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 3.0% of Note 4:
Rated Thermal Power.
s l
REACTIVITY CONTROL SYSTEMS BASES B0 RATION SYSTEMS (Continued)
Refuelina Water Storaae Tank Reauirements for Maintainina SDM - Modes 1-4 Required volume for maintaining SDM presented in the COLR Unusable volume (below nozzle) 16,000 gallons Additional margin 17,893 gallons With the RCS temperature below 200*F, one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection System becomes inoperable.
I 1
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 300*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 1% delta k/k after xenon decay and cooldown from 200*F to 140*F. The minimum borated water volumes and concentrations required to maintain shutdown margin for the Boric Acid Storage System and the Refueling Water Storage Tank are presented in the Core Operating Limits Report.
The Technical Specification LC0 value for the Boric Acid Storage Tank and the Refueling Water Storage Tank minimum contained water volume during Modes 5 and 6 is based on the required volume to maintain shutdown margin, an allowance for unusable volume and additional margin as follows:
Boric Acid Storace Tank Reouirements for Maintainino SDM - Modes 5 & 6 Required volume for maintaining SDM presented in the COLR Unusable volume (to maintain full suction pipe) 4,132 gallons l
Additional margin 1,415 gallons Refuelina Water Storaae Tank Reauirements for Maintainina SDM - Modes 5 & 6 Required volume for maintaining SDM presented in the COLR Unusable volume (below nozzle) 16,000 gallons Additional margin 6,500 gallons The contained water volume limits include allowance for water not avail-able because of discharge line location and other physical characteristics.
McGUIRE - UNITS 1 and 2 B 3/4 1-3 Amendment No. 143 (Unit 1)
Amendment No. 125 (Unit 2)