ML20082A764
| ML20082A764 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/29/1995 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20082A762 | List: |
| References | |
| NUDOCS 9504040220 | |
| Download: ML20082A764 (12) | |
Text
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i Docket No. 50-423 B15166 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Reactor Coolant System Flow Rate Marked-Up Pages i
)
March 1995 l
9504040220 950329 DR ADOCK 05000423 PDR
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March 1,,. 'i991 Q
TAbtE 2.2-1 g-
/
3x REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS EP
- tC; TOTAL SENSOR g
ALLOWANCE ERROR R
FUNCTIONAL UNIT (TA)
I (S)
TRIP SETPOINT ALLOWABLE VALUE l.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
Ep 2.
Power Range, Neutron Flux
,u a.
High Setpoint
- 1) Four Loops Operating 7.5 4.56 0
$ 109% of RTP**
$ 111.1% of RTP**
- 2) Three Loops Operating 7.5 4.56 0
s 80% of RTP**
s 82.1% of RTP**
l b.
Low Setpoint 8.3 4.56 0
1 25% of RTP**
s 27.1% of RTP**
3.
Power Range, Neutron Flux, 1.6 0.5 0
s 5% of RTP** tith 5 6.3% of RTP** with High Positive Rate a time constant a time constant 1 2 seconds 1 2 seconds m
di 4.
Power Range, Neutron Flux, 1.6 0.5 0
1 5% of RTP** with 5 6.3% of RTP** with High Negative Rate a time constant' a time constant 1 2 seconds 2 2 seconds.
5.
Intermediate Range, 17.0 8.41 0
$ 25% of RTP**
$ 30.9% of RTP**
i Neutron riux l'g 6.
Source Range, Neutron Flux 17.0 10.01 0
1 10+5 cps i 1.4 x 10+5 cp3 )
h 7.
Overtemperature AT
!E f
a.
Four Loops Operating lg 6-i'l 1' C '
)
- 1) Channels I, II 10.0 60-
+rH- + - 1.33 See Note 1 See Note 2 f
5 717-Q y + Press)
- 2) Channels III, IV 10.0
-5 63-
-hf+ + 2.60 See Note 1 See Note 2 (Temp + Press)
- RTP - RATED THERMAL POWER l
.y._
's March 11, 1991 TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUNENTATION TRIP SETPOINTS U
TOTAL SENSOR S
ALLOWANCE ERROR 7
FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE b.
Three Loops Operating
- 1) Channels I, II 10.0 6.80 1.71 + 1.33 See Note 1 See Note 2 w
(Temp + Press)
- 2) Channels III, IV 10.0 5.83 1.71 + 2.60 See Note 1 See Note 2
/
(Temp + Press)
[
t -2 9 t.c i omb)4.8 8.
Overpower AT ( %wlwes r 3
-k24
-h7P See Note 3 See Note 4 l-9.
Pressurizer Pressure-Low 5.0 1.77 3.3 2 1900 psia 1 1890 psia
- 10. Pressurizer Pressure-High 5.0 1.77 3.3 s 2385 psia i 2395 psia m
11.
Pressurizer Water Level-High 8.0 5.13 2.7 s 89% of instrument S 90.7% of instrument span span
- 12. Reactor Coolant Flow-Low 2.5 1.52 0.78 190% of loop 189.1% of loop design flow
- design flow
- F e
- 13. Steam Generator Water 18.10 16.64 1.50 118.10% of narrow 117.11% of narrow l
Level Low-tow range instrument range instrument g
span span r+
y
- 14. General Warning Alarm N.A.
N.A.
N.A.
N.A.
N.,A.
,w
- 15. Low Shaft Speed - Reactor 3.8 0.5 0
2 95.8% of rated
'l 92.5% of rated P
Coolant Pumps speed speed
- w
- w g
- MinimumMeasuredFlowPerLoop-66, ourLoopsOperating);(01,066 (Three Loops Operating)-
Vi o F h MS PW fRR -
y3 g _gg gcs p:tou paktS m b
.ki vw E' e \\(dea A SetW m 3.t-3-1.-CL RS W d A k (W m ~1.2 3.'2.ct 1
paw s
March 11,11991 5
TABLE 2.2-1 (Continued) 4 H r-M
-TABLE NOTATIONS (Continued)
- o. E
('"
~ NOTE 1:
(Continued)
E T'
1 587.l*F (Nominal T,yg at RATED THERMAL POWER);
r p
.\\
a w
K 0.001311/ psi;
=
3
~
P Pressurizer pressure, psia; P'
2250 psia (Nominal RCS operating pressure);
=
Laplace transform operator, s 1; S
powerI(AI) is a function of the indicated difference between top and bottom detectors of the and f range neutron ion chambers;-with gains to be selected based on measured instrument response y
during plant startup tests such that:
s
- qb between -26% and + 3%, f (AI) - 0, where q "d ab are percent RATED THERMAL POWER I
(1)
Forqktopandbottomhalvesofthecorerespectively,t"dqt+9 i
in th an is total THERMAL POWER in b
l percent of RATED THERMAL POWER;
(-
(2)
For each percent that the magnitude of q, - qs exceeds -26%, the AT Trip Setpoint shall be automatically reduced by 3.55% of its value at RATED -THERMAL' POWER; and 1
t 37 (3)
For each percent that the magnitude of q - qu exceeds +3%, the AT Trip Setpoint shall be l @
automatically reduced by 1.98% of its va,ue at RATED THERMAL POWER.
T J
+
a.
! M
( - L+ %
5 NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than Q s
,5 AT span (Four Loop Operation); 2.7% AT span (Three Loop Operation).
g;
\\
l
[
U 1
Ig
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10/25/93 Table 2.2-1 (Continued)
TABLE NOTATIONS _iContinued) 1 i
NOTE 3:
(Continued)
K 0.00180/*F for T > T" and K6 - 0 for T 1 T",
6 T
As defined in Note 1, T"
Indicated T,q at RATED THERMAL POWER (Calibration temperature for AT instrumentation, 5 587.1*F),
i S
As defined in Note 1, and f(AI) 0 for all AI.
2 NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.7% AT span, Crow Loop o pes-no O.
I NOTE 5:
Setpoint is for increasing power.
I NOTE 6:
Setpoint is for decreasing power.
NILLSTONE - UNIT 3 2-12 Amendment No. pp,85 es W eTtV h
March 11, 1991
'~
POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3.2.T;1 'The indicated Reactor Coolant System (RCS) total flow rate and F AH shall be maintained as follows:
RCS total flow rate 2 Mpm,,9%O 3 78 and a.
N R P [1.0 + PFAH (1.0 - P)]
b.
F3H s F3 Where:
THERMAL POWER 1)
P
=
l_
RATED THERMAL POWER N
2)
Measured values of F obtained by using the movable F
ikH =
detectors to tain a power distribution map.
The AH core measured value of should be used since Specifica-tion 3.2.3.lb.takesin[o"considerationameasurementuncertainty of 4% for incore measurement, RTP N
3)
F
= The F LNITS REPORfH(11mit at RATED THERMAL POWER COLR),.
N 4) ankg - The power factor multiplier for F3Hprovided in the COLR, PF
'5)
The er.sured value of RCS total flow rate shall be used since uncertainties of 2.4% for flow measurement have been included in Specification 3.2.3.la.
/
APPLICABILITY: MODE 1.
ACTION:"
'With the RCS total flow rate or FfH outside the region of acceptable operation:
a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
1.
Restore the RCS total flow rate and F to within the above H
limits, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and I
reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
M..ILLSTONE - UNIT 3 3/4 2-19 AmendmentJJ,#.h a
'.~
/
Docket No. 50-423 B15166 l
Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Reactor Coolant System Flow Rate Retyped Pages March 1995 t-
TABLE 2.2-1 15 ACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR ig p
ALLOWANCE ERROR.
3 FUNCTIONAL UNIT fTA)
I (S)
TRIP SETPOINT ALLOWABLE VALUE E
m 1.
Manual Reactor 1+1p N.A.
N.A.
N.A.
N.A.
N.A.
j g
2.
Power Range, Neutron Flux
[
a.
High Setpoir:t
- 1) Four Loops Operating 7.5 4.56 0
$ 109% of RTP**
1 111.1% of RTP**
- 2) Three Loops Operating 7.5 4.56 0
s 80% of RTP**
$ 82.1% of RTP**
b.
Low Setpoint 8.3 4.56 0
5 25% of RTP**
$ 27.1% of RTP**
l 3.
Power Range, Neutron Flux, 1.6 0.5 0
5 5% of RTP** with s 6.3% of RTP** with High Positive Rate a time constant a time constant-1 2 seconds 1 2 seconds i
m 4,
4.
Power Range, Neutron Flux, 1.6 0.5 0
1 5% of RTP** with 1 6.3% of RTP** with High Negative Rate a time constant a time.' constant-1 2. seconds 1 2 seconds 5.
Intermediate Range, 17.0 8.41 0
5 25% of RTP**
$ 30.9% of RTP**
Neutron Flux 6.
Source Range, Neutron Flux 17.0 10.01 0
1 10+' cps 1 1.4 x 10+' cps 7.
Overtemperature AT
]
g a.
Four Loops Operating E
- 1) Channels I, II 10.0 8.14.
1.61 + 1.33 See Note 1 See Note 2 y
(Temp + Press)
(
- 2) Channels III, IV 10.0 7.17 1.61 + 2.60 See Note 1-See Note 2
?*
(Temp + Press)
I 1
~ '
- RTP = RATED THERMAL POWER 4
i
~
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS o :s TOTAL SENSOR ALLOWANCE ERROR k
FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE b.
Three Loops Operating
- 1) Channels I, II 10.0 6.80 1.71 + 1.33 See Note 1
'See Note 2 (Temp + Press)
- 2) Channels III, IV 10.0 5.83 1.71 + 2.60 See Note 1 See Note 2 (Temp + Press) 8.
Overpower AT (Four Loops Operating) 4.8 1.28 1.61 See Note 3 See Note 4 l
9.
Pressurizer Pressure-Low 5.0 1.77 3.3 1 1900 psia 1 1890 psia 10.
Pressurizer Pressure-High 5.0 1.77 3.3 1 2385 psia 1 2395 psia 11.
Pressurizer Water Level-High 8.0 5.13 2.7 s 89% of instrument S 90.7% of instrument 4
span span 12.
Reactor Coolant Flow-Low 2.5 1.52 0.78 190% of loop 189.1% of loop design flow
- design flow *
- 13. Steam Generator Water 18.10 16.64 1.50 1 18.10% of narrow 117.11% of narrow Level Low-Low range instrument range instrument span span kg
- 14. General Warning Alarm N.A.
N.A.
N.A.
N.A.
N.A.
Es 15.
Low Shaft Speed - Reactor 3.8 0.5 0
1 95.8% of rated 1 92.5% of rated Coolant Pumps speed speed E
D.
D
- Minimum Measured Flow Per Lcop - 1/4 of the RCS Flow Rate Limit as listed in Section 3.2.3.1.a (Four Loops Operating);
(
1/3 of the RCS Flow Rate Limit as listed in Section 3.2.3.2.a (Three Loops Operating)
?
4 m
'*a y
y E
~
Q TABLE 2.2-1 (Continued) k TABLE NOTATIONS (Continued) h NOTE 1:
(Continued)
T' 1 587.1*F (Nominal T,yg at RATED THERMAL POWER);
0.001311/ psi; K
3 Pressurizer pressure, psia; P
=
2250 psia (Nominal RCS operating pressure);
P' Laplace transform operator, s- ;
S and f (AI) is a function-of the indicated difference between top and bottom detectors of the 7
'?
power-range neutron ion chambers; with gains to be selected based on measured instrument response 5
during plant startup tests such that:
between -26% and + 3%, f,(AI) = 0,. where q and q are percent RATED THERMAL POWER (1)
For q, - qb in the top and bottom halves of the core respectively,t and q percent of RATED THERMAL POWER;
'+ qb is total THERMAL POWER in (2) ForeachpercentthatthemagnitudeofqlueatRATEDTHERMALPOWER;andexceeds -26%, the AT Trip Setp
- qs automatically reduced by 3.55% of its va (3) For each percent that the magnitude of q - qs exceeds +3%, the AT Trip Setpoint shall be automatically reduced by 1.98% of its vafue at RATED THERMAL POWER.
- s g
NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 1.4%
l g
AT span (Four Loop Operation); ~d.7% AT span (Three Loop Operation).
f J
m
+
4 x
.._,w
9
( :,.i*g.
h:n TABLE 2.2-1 (Continued)
M E
TABLE NOTATIONS (Continued) m EQ NOTE 3:
(Continued) u 0.00180/*F for T > T" and K6 - 0 for T 1 T",
K 6
T As defined in Note 1, T"
Indicated T,yg at RATED THERMAL POWER (Calibration temperature for AT instrumentation, 5 587.l*F),
As defined in Note 1, and S
f (AI) 0 for all AI.
2 NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.7% AT span. (Four Loop Operation) l NOTE 5:
Setpoint is for increasing power.
l l
NOTE 6:
Setpoint is for decreasing power.
l l
l I
l 1
I a
.F l
=
..e.
r-
.c
' S. ~
f PONER DISTRIBINION LINITS
-3/4 t.3 RCS FLOW RATE AM NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR
-b F0tB LOOPS OPERATING LINITING C0M ITION FOR OPERATION 3.f.3.1 The indicated Reactor Coolant System (RCS) total flow rate and FE shall be, maintained as follows:
a.
RCS total flow rate 2,371,920 gps, and i
b.
F51 Fm" [1.0 + PF, (1.0 - P)]
Where:
THERMAL POWER yy p,
RATED THERMAL POWER, 2)
FE =
Measured values of FE obtained by using the movable incore detectors go obtain a power distribution map.
The measured value of Fu should be used since Specification 3.2.3.lb.
takes into consideration a measurement uncertainty of 4% for incore measurement, 3)
Fm" - The FE limit at RATED THERMAL POWER in the CORE OPERATING LIMITS REPORT (COLR),
g 4)
PFm - The power factor multiplier for FE provided in the COLR, and 5)
The measured value of RCS total flow rate shall be used since uncertainties of 2.4% for flow measurement have been included in Specification 3.2.3.la.
APPLICABILITY: MODE 1.
3 ACTION:
With the RCS total flow rate or FE outside the region of acceptable operation:
a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
1.
Restore the RCS total flow rate and FE to within the above limits, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Set)oint to less than or equal to 55% of RATED THERMAL POWER wit 11n the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(
NILLSTONE - UNIT 3 3/4 2-19 Amendment No. JJ JJ, JP t'
0181 w
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