ML20053E635
| ML20053E635 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/08/1982 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20053E618 | List: |
| References | |
| NUDOCS 8206090097 | |
| Download: ML20053E635 (8) | |
Text
'
ENCLOSURE 3 North Anna Technical Specifications Changes for Tavg of 582.8 F t
1 t
I i
l l
l t
i i
l 3
i 8206090097 820608 l
PDR ADOCK 05000338 P
[
TABLE 2.2-1 (Continuzd) 5 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS W
NOTATION Diz
~1+t S' g
NOTE 1: Overtemperature AT1T [K -K (T-T')+K
}1 OI
~
g 2 3
g 1+t 8 2-e Where: AT O
T
= Average temperature. 'F T'
= Indicated T at RATED THERMAL POWER 1 582.8 F P
= Pressurizer pressure, psig P'
= 2235 psig (indicated RCS nominal operating pressure)
= The function generated by the lead-lag controller for T,yg dynamic compensation N
1+t S 1
f, 1+t 8 2
r
= 25 sees,
- 1
'2
= Time constantssatilized in the lead-lag controller for T**8 t
= 4 secs.
2
=Laplacetransformoperator(sech
~
S
TABLE 2.2-1 (ContinuGd)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS z
O NOTATION (Continued)
E Operation with 2 Loops Operation with 2 Loops Operation with 3 Loops (no loops isolated)*
(1 loop isolated)*
8 6
(
)
(
)
K
=
1.113 K
g
=
g K
=
g
(
)
(
)
K K
2 0.0132 2
K
=
2
(
)
(
)
K
=
0.000628 K
3
=
K 3
=
3 of the power-range nuclear ion chambers; with gains to be selected based on measur and f instrument response during plant startup tests such that:
between - 35 percent and + 7 percent, f (AI)
=0 g
arepercentRATEDTHERMALPOWERinthetopandbottom (1) for q 9
t b
(where q and qb
'f halvesofthecorerespectively,andq is total H E N M ER in
- Sb
'o t
percent of RATED THERMAL POWER).
q ) exceeds - 35 percent, for each percent that the magnitude of (q (ii) b the AT trip setpoint shall be automatically reduced by 1.21 percent of its value at RATED THERMAL POWER.
for each percent that the magnitude of (q qb) exceed 8 +7 Percent, (iii) theATtripsetpointshallbeautomaticalkyreducedby1.09percentof its value at RATED THERMAL POWER.
l
- Values dependent on NRC approval of ECCS evaluation for these operating conditions.
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOTATION (Continued) d:c
^
T 8 3
6 (T-f )-f (0 }1 K
T NOTE 2:
Overpower AT1 AT,[K -K5 2
4 1+T 8 3
l y
Indicated AT st RATED THERMAL POWER i
J Where:
AT
=
o e-I
- F Average temperature.
T
=
~
Indicated T at RATED THERMAL POWER 1582.8'F T"
=
.088 K
=
4 0.02r F for increasing average temperature K
=
3 w
0 for decreasing average temperatures K
=
5 o
1" 0.00119 for T > T"; K
= 0 for T T
K
=
6 6
The function generated by the rate lag controller for T,yg T S
=
3 dynamic compensation 1+T S 3
Time constant utilized in the rate lag controller for T**E t
10 secs.
T
=
3 Laplace transform operator (see 1)
S
=
z f (AI) = 0 for all Al 2
The channel's maximum trip point shall not exceed its computed trip point by more than Note 3:
2 percent span.
TABLE 3.2-1 DNB PARAMETERS _
lb 4m LIMITS 2 Loops In Operation **
2 Loops In Operation **
z 3 Loops In
& Loop Stop
& Isolated Loop E
PARAMETER Operation Valves Open Stop Valves Closed 8
U
<587'F w
>2205 psig*
Pressurizer Pressure
>278,400 gpa Reactor Coolant System Total Flow Rate R
s~
Y0
- Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER.
- Values dependent on NRC approval of ECCS evaluation for these conditions.
1 i
l l
l
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUltENT\\ TION TRIP SETPOINTS g
NOTATION g
g 1
'1+T s g
NOTE 1: Overtemperature AT < T [K -K (T-T' )+K (P-P' )-f (61) ]
9 y 2 3
y g
1+T 82_
g e
N Where: AT
~ " ""
- O T
= Average temperature. *F T'
= Indicated T at RATED THERMAL POWER < 582.8 F avg l
P
= Pressurizer pressure, psig P'
= 2235 psig (indicated RCS nominal operating pressure) 1
= The function generated by the lead-lag controller for T,yg dynamic compensation 1+T S "d
1+T S 2
T
= 25 secs.
1 2
= Time constants utilized in the lead-lag controller for T**E 4 secs.
T a
2
~
S
= Laplace transform operator (sec )
1 e
b w
s,
TABI.E 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP S6TPOINTS m
@y
- ~
i NOTATION (Continued)
E>
Operation with 3 Loops Operation-with 2 Loops Operation vie 2 Loops (no loops isolated)*
(1 loop isclated)*
E s
(
)
(
)
K
=
1.113 K
=-
g g
g y
K
=
( m\\ '
(
)
)
K w
Kg
=
0.0132 2
K
=
2
(
)
K
(
)
0.000628 K
=
3 3
K
=
?i 3
g (AI) is a function of the indicated difference between top and bottom detectors and f of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup te'ts such that:
s.
t 7 percent, f (al)
=0 between - 35 percent and +
(i) for q
- 9 arepercentRATEDTHERMALPOWERinthetopandbottom t
b 7
(where q and qb
+
is total THERMAL POWER in halvesofthecorerespectively,andq qb percent of RATED THERMAL POWER).
t for each percent that the magnitude of (q
- g ) exceeds - 35 percent,
, (ii) b the AT trip setpoint shall be automatically reduced by 1.21 percent of its value at RATED THERMAL POWER.
for each percent that the magnitude of (q qb) exceeds + 7 percent, (iii) the AT trip setpoint shall be automatica1Iy reduced by 1.09 percent of its value at RATED THERMAL POWER.
i
(
- Values dependent on NRC approval of ECCS evaluation for these operating conditions.
l
TABLE 3.2-1 DNB PARAMETERS 4x LIMITS 2 Loops In Operation **
2 Loopa In Operation **
z#
3 Loops In
& Loop Stop
& Isolated Loop PARAMETER Operation Valves Open Stop Valves Closed 5
N
<587'F l
Reactor Coolant System T avg
>2205 psig*
Pressurizer Pressure
>278,400 gpm Reactor Coolant System Total Flow Rate M
- ~
Y 5
- Limit not applicable during either a THERMAL POWER ramp -increase in excess of 5% RATED TilERMAL POWER per minute or a THERMAL POWER step therease. in excess of 10% RATED TilERMAL POWER.
- Values dependent on NRC approval of ECJS evaluation for these conditions.
.