ML20077F114
| ML20077F114 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/02/1994 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20077F113 | List: |
| References | |
| NUDOCS 9412130271 | |
| Download: ML20077F114 (6) | |
Text
,
l Docket No. 50-423 B15039 Millstone Unit No. 3 Proposed Revinion to Technical Specifications Reactor Trip System Instrumentation Surveillance Requirements Change Marked-Up Pages December 1994 941213o271 941202 PDR ADOCK 050C 0423 P
ppq
IABLE 4.3-1
^ex REACTOR TRIP SYSTEM INSTRUENTATION SURVEILLANCE REOUIREMDITS J :';-
4, m
TRIP 3
ANALOG ACTWTIM IRIDES FOR m
CHANNEL DEVICE WHICN CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTURTION SURVEILURE E
FWCTIONAL WIT CHECK CALIBRATION TEST IEST LOGIC.TESI IS MOUIRED
[
1.
Nansal Reactor Trip N.A.
N.A.
N.A.
R(14,20)
N.A.
1,2,3*,4*L.:
5*
I u
2.
Power Range, Neutron Flux l
a.
High Setpoint S
D(2,4),
Q N.A.
R.A.
1, 2 M(3,4),
i r
Q(4,6),
R(4,5,20) b.
Low Setpoint S
R(4, S/U(1)
N.A.
M.A.
1***,2
\\
i w1 3.
Power Range, Neutron Flux, M.A.
R(4. 20)
Q N.A.
N.I.
1, 2 High Positive Rate L
5g o
4.
Power Range, Neutron Flux.
N.A.
R(4(20)
Q N.A.
N.A.
1, 2 High Negative Rate g
5.
Intermediate Range S
R(4.5)
S/U(1)
N.A.
M.A.
1***, 2 6.
Source Range Neutron Flux S
R(4. 5)
S/tf(l),
N.A.
N.A.
2**, 3, 4, Q(9) 5 7.
Overtemperature AT R
Q N.A.
N.A.
1, 2 g
p h.
8.
Cla w ;. AT S
R Q
N.A.
N.A.
1, 2 f
E 2
.o g.
Pressertzer Pressure--Low S
R(20)
Q(18)
N.A.
N.A.
1
):
$ ~
10.'
Pressurizer Pressure--Nigh 5
R(20)
Q(18)
N.A.
R.A.
1, 2 D'
M w-
- 11. Itessurizer Uater. level--Nigh-5 R(20)
Q..
. N.A.
.N.A.
1 r
1 12 teacter Coolant Flow--Low 5
R(20' 4
N.A.
N.A.
k
1.
12/22I92 TABLE 4.3-1 (Continued)'
TABLE NOTATIONS When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.
Below P 6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- 8elow P-10 (Low setpoint Power Range Neutron Flux Interlock) Setpoint.
- Above the P-9 (Reactor Trip / Turbine Interlock) Setpoint.
(1) If not performed in previous 31 days.
(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 greater than 2%.
The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.
(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above i
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 applicable for entry into MODE 2 or 1.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
s euw e Ru+f (5) Detector plateau curves shall b obtained, and evaluated and compared to Flux channels the provisions'(intermediate Range and Power Range Neutron manufacturer's data.
For the 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)
(Not used)
I (9) Quarterly surveillance in MODES 3*,
4*,
and 5*
shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.
t STONE - UNIT 3 3/4
-13 Amendment No pp, 70
c,,
3.-
Docket No. 50-423 B15039 l
Millstone Unit No. 3 Proposed Revision to Technical Specifications Reactor Trip System Instrumentation Surveillance Requirements Change Retyped Pages 1
l December 1994
nx 0;:
TABLE 4.3-1 0;
y REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR E
CHANNEL DEVICE WHICH q
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS RE0UIRED 1.
Manual Reactor Trip N.A.
N.A.
N.A.
R(14,20)
N.A.
g 2, 3*, 4*,
2.
Power Range, Neutron Flux a.
High Setpoint S
Di;2,41 Q
N.A.
N.A.
1, 2 Mi,3,4?,
,'20) b.
Low Setpoint S
R(4, 5, 20)
S/U(1)
N.A.
N.A.
1***, 2 3.
Power Range, Neutron Flux, N.A.
R(4, 5, 20)
Q N.A.
N.A.
1, 2 w)
High Positive Rate Y
4.
Power Range, Neutron Flux, N.A.
R(4,5,20)
Q N.A.
N.A.
1, 2 g
High Negative Rate 5.
Intermediate Range S
R(4,5)
S/U(1)
N.A.
N.A.
1***,
2 6.
Source Range, Neutron Flux S
R(4,5) 1),
N.A.
N.A.
g**,3,4, g
7.
Overtemperature AT S
R Q
N.A.
N.A.
1, 2 R
8.
Overpower AT S
R Q
N.A.
N.A.
1, 2 Eg 9.
Pressurizer Pressure--Low S
R (20)
Q(18)
N.A.
N.A.
1 g
10.
Pressurizer Pressure--High S
R (20)
Q(18)
N.A.
N.A.
1, 2 11.
Pressurizer Water Level--High S R (20)
Q N.A.
N.A.
1 g
(
12.
Reactor Coolant Flow--Low S
R (20)
Q N.A.
N.A.
I
?
4
i,
.g.-
3 TABLE 4.3-1 (Continued)
TABLE NOTATIONS When the Reactor Trip System breakers are closed and the Control Rod Drive System.is capable of rod withdrawal.
Below P 6 (Intermediate Range Neutron Flux Interlock) Setpoint.
Below P-10 (Low Satpoint Power Range Neutron Flux Interlock) Setpoint.
i
(
Above the P-9 (Reactor Trip / Turbine hurlock) Setpoint.
l (1)
If not performed in previous 31 days.
j (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 greater than 2%.
The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.
j (3)
Single point comparison of incore 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 l
uot applicable for entry into MODE 2 or 1.
j (4)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5)
Detector plateau curves shall be obtained, and evaluated and compared to manufacturer's data. For the Source Range, 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)
(Not used)
(9)
Quarterly surveillance in MODES 3*,
4*,
and 5* shall also include verification that permissives P-6 and P-10 are in their required state 1
for existing plant conditions by observation of the permissive annunciator window.
NIgLSTONE-UNIT 3 3/4 3-13 Amendment No. pp 79,