ML20059E535
| ML20059E535 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/04/1990 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20059E534 | List: |
| References | |
| NUDOCS 9009100226 | |
| Download: ML20059E535 (6) | |
Text
. = =..... _ _ _ _ _ _
ATTACHMENT 2 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGAs LICENSE APPLICATIO11 90-03, NLR-N90059 ELIMINATION OF APRM DOWNSCALE TRIP The following Technical Specifications have been revised to reflect the proposed changes T,g,chnical Specification Index Pace Table 2.2.1-1, Itom 2e 2-4 Table 3.3.1-1, Iten 2e 3/4 3-2 Table 3.3.1-2, Item 2e 3/4 3-6 Table 4.3.1.1-1, Item 2e 3/4 3-7 9009100226 900904 FDR ADOCK 0500C'3'54 P
TARLE 2.2.1-l~
.I REACTOR PROTECTION SYSTEN INSIMBIENTATION SETPOINTS
=
. { FUNCTIONAL UNIT TRIP SETFOINT Ati.0 WASTE VMUES
~
1.
Intermediate Range Monitor,lleutron Flux-High 5 120/125 divisions' 1.122/125 divisions i
of. full scale 2.
Average Power Range Monitor:
of fall' scale
[
a.
IIeutron Flux-$ scale, Setdown 5 ISE of RATED TEWint POWER
$ 28K'ef RATES 1Eluthl. POWER-
.j b.
Flow Biased Simulated Thermal Power-5 scale
- 1) Flow Biased
~< 0.66(w-aw)+51%** with
< 0.66(w-aw)+545**
O U
a maximum of
- with a maniaun of i
- 2) High Flow Clauped 5 113.5% of RATED
< '115.5E of RATED
}
i TEWIAL POER
- T E NIAL PO E R o
c.
Fixed liestron Flu-Upscale
< 118E of RATED THEMIAL POWER.
.i m
1
< 120E of R4iig d
-THENERL POWit d.
Inoperative M4 11 4
+
m-n t.
9/.
s mer ma matra
_s a ser _a mawr=
-T 3.
Reactor Vessel Steam Dame Pressure - High 5 1837 psig.
- $ 1957 psig j
4.
Reacter Vessel Water Level - Low, Level 3
-> 12.5 inches'above instrument
> 11.9 inches above zere* '
lastrennent zere?
a g
5.
Main Steam Line Isolation Valve - Closure
$ SE closed 5 125' closed h
- 5ee Bases Figure 8 3/4'3-1..
~
E **The Average Power Range Monitor Scran function varies as a function of recirculation loop drive flew (w)..
g aw is defined as the difference in indicated' drive flow (in percent of drive flew which produces' rated-core flow) between two'1oep and single loop' operation at.the same core flow. 'aw = 0 for two recirculation'-
loop operation. 'aw = "To be determined at a'later date" for single recirculation loop operation.
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TABLE 4.3.L l-1 i
A REACTOR PROTECTIDN SYSTEN INSTRtMENIAll0N SHRVEILLANCE REQUIREE N15 1
o E
CH4ididL
~
, OPERATIONAL 9E CHAMEL FUNCTIONAL CHANNEL C0181TIONSFORtRMCMif
^
FUNCTIONAL UNIT-CHECK TEST CAtIBRATION "),
SURVEILLANCE REQUIREST 1
I 1.
{/(b).3 Sjg(c)*y g-2 a.
htNtron fisr. - High t
y g
3,4,5 b.
Inoperative M
W NA
~2, 3,~4, 5 i
I 2.
Average Power 4nge Monitor S i
a.
- Netstron Flux - '
S/U(b) 5 S/U(c),W SA 2
'f a
tipsca.le, Ieldomi 5
W SA -
' 3, 4, 5 w
b.
Flow ~ Biased Simulated I9I IC)
Id}I') SA.R '}
')
d
)
Thermal Power - Upscale 5,0 O
S/U
., Q W
4 c.
Fixed Neutron Flux -
Upscale 5j (c),q' y(d), Sg 11 l
d.
Inoperative NA Q
NA-1,'2, 3, 4, 5
[
't i
.c-u_-.
ej C
g n - - gig _
3.
Reactor Vessel. Steam Dome II Pressure - High 5'
Q R
1, 2 '
-l 4.
t i
[
Low, Level 3 S'
Q(k)
R l','2-l:
s
[
5.
Main Steam Line' Isolation h
a Valve - Closure NA' q
R 1
.I
/
,+
1
& - 6.
Main Steam Line Radiation -
II) l High,.High' S
Q R
.~1, 2 I
h3 7.
Drywell.
Pressure - High.
S Q(k)
R 1, 2 l
t
~
+
r i) 4
-4
- 6 t'
i ATTAQDODIT 3 GENERAL ELECTRIC' REPORT JUSTIFYING
't PROPOSED TECHNICALLSPECIFICATION.. CHANGE 7
i LICENSE APPLICATION 90-03, NLR-N90059.
' ELIMINATION OF APRN DOWNSCALE TRIP:
l 2
i
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s i
1.
c l
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