ML20062L303
| ML20062L303 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/17/1993 |
| From: | Plisco L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062L306 | List: |
| References | |
| NUDOCS 9312290278 | |
| Download: ML20062L303 (23) | |
Text
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2-I 'A E
UNITED STATES i
NUCLEAR REGULATORY COMMISSION gs
,/
WASHINGTON. D.C. 20555-0001 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.113 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated October 25, 1993, as supplemented December 3 and 6, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as-amended (the Act), and the Comission's rulc and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
$$k Dbh k3 P
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.113, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7
~
/
V L-Loren R. Plisco, Acting Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification l
Changes Date of Issuance:
December 17, 1993 t
4
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puray%
p O
E UNITED STATES I
3 NUCLEAR REGULATORY COMMISSION
't
,/
WASHINGTON, D.C. 20555-0001 y
DUKE POWER COMPANY i
NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY
)
DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 107 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (licensees), dated October 25, 1993, as supplemented December 3 and 6, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the 1
Comission's rules and regulations as set forth in 10 CFR Chapter I
I; B.
The facility will operate in conformity with the application, the 3
provisions of the Act, and the rules and regulations of the j
Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's reguhtions set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon i
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1
! 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.107, and the Environmental Protection Plan contained in Appendix 3, both of which are attached hereto,-are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A.4 Loren R. Plisco, Acting Direct r Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
December 17, 1993
'i
4 f
ATTACHMENT TO LICENSE AMENDMENT NO.113 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 ANQ TO LICENSE AMENDMENT N0.107 FACILITY OPERATING LICENSE NO. NPF-52 l
DOCKET NO. 50-414 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes III III IV IV Va Va 1
2-2 2-A2 2-B2 2-4 2-A4 2-B4 2-7 2-A7 l
2-B7 2-8 2-A8 2-B8 2-9 2-A9 2-B9 l
2-10 2-A10 i
2-B10 2
3/4 2-16 3/4 A2-16 l
3/4 B2-16 j
i l
l
4 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS I
k SECTION PAGE 2.1 SAFETY LIMITS i
2.1.1 R E AC TO R C0 R E...............................................
2 - 1 2.I.2 REACTOR COOLANT SYSTEM PRESSURE............................
2-1 FIGURE 2.1-la REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION - UNIT 1..............................
2-A2 l
4 FIGURE 2.1-lb REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION - UNIT 2..............................
2-B2 l
)
2.2 LIMITING SAFETY SYSTEM SETTINGS j
2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS..............
2-3 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS...
2-4 BASES SECTION 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE.............................................. B 2-1 I
2.1.2 REACTOR COOLANT SYSTEM PRESSURE........................... B 2-2 i
1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0lNTS...............B 2-3 i
CATAWBA - UNITS 1 & 2 III Amendment No.113 (Unit 1)
Amendment No.107 (Unit 2)
r 4
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION EA_GE y
3/4.0 APPLICABILITY 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL Shutdown Margin - T,,, > 200*F 3/4 1-1 Shutdown Margin - T,,, s 200*F 3/4 1-3 Moderator Temperature Coefficient 3/4 1-4 Minimum Temperature for Criticality 3/4 1-6 3/4.1.2 B0 RATION SYSTEMS Flow Path - Shutdown...................
3/4 1-7 Flow Paths - Operating..................
3/4 1-8 Charging Pump - Shutdown.................
3/4 1-9 Charging Pumps - Operating................ 3/4 1-10 Borated Water Source - Shutdown (Unit 1)........
3/4 Al-11 Borated Water Source - Shutdown (Unit 2)........
3/4 B1-11 Borated Water Sources - Operating (Unit 1).......
3/4 Al-12 Borated Water Sources - Operating (Unit 2).......3/4 B1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.......................
3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R00..........
3/4 1-16 Position Indication Systems - Operating 3/4 1-17 Position Indication System - Shutdown 3/4 1-18 Rod Drop Time 3/4 1-19 Shutdown Rod Insertion Limit...............
3/4 1-20 Control Bank Insertion Limits 3/4 1-21 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - FQ(X,Y,Z) 3/4 2-3 l
CATAWBA - UNITS 1 & 2 IV Amendment No. 113 (Unit 1)
Amendment No. 107 (Unit 2)
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAGE 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.......... 3/4 2-7 l
3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-10 l
3/4.2.5 DNB PARAMETERS......................
3/4 2-13.
l TABLE 3.2-1 DNB PARAMETERS....................
3/4 2-15 l
FIGURE 3.2-1 REACTOR COOLANT SYSTEM TOTAL FLOW RATE VERSUS RATED THERMAL POWER-FOUR LOOPS IN OPERATION (UNIT 1) 3/4 A2-16 FIGURE 3.2-1 REACTOR COOLANT SYSTEM TOTAL FLOW RATE VERSUS RATED THERMAL POWER-FOUR LOOPS IN OPERATION (UNIT 2)......
3/4 82-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES...
3/4 3-7 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................
3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-13 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-15 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3/4 3-27 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES......
3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-42 CATAWBA - UNITS 1 & 2 Va Amendment No. 113 (Unit 1)
Amendment No. 107 (Unit 2)
UNIT 1 ONLY 670 DO NOT OPERATE IN THIS AREA 660 650 2455 psia 2400 psla b630 2280 psic
?
,9 b620 2100 psia 610 1945 psia 600 590 ACCEPTABLE OPERATION g
0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power Figure 2.1-1a REACTOR CORE SAFETY LIMITS - FOUR LOOPS IN OPERATION 382,000 gpm CATAWB A - UNIT 1 2-A2 Amendment No. 113
UNIT 2 ONLY 3
670 DO NOT OPERATE IN THIS AREA.
660 g
2455 psia 640 2400 psio C
2280 psio 630 om
,9
.m N
~
2100 psic 610 1945 psia 600 590 ACCEPTABLE OPERATION 1
t t
t g
0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Roted Thermal Power Figure 2.1-1b REACTOR CORE SAFETY LIMITS - FOUR LOOPS IN OPERATION 385,000 gpm CATAWB A - UNIT 2 2-B2
/Jaendment No'; _107
UNIT 1 ONLY TABLE 2.2-1 h
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E
2" FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE E
1.
Manual Reactor Trip N.A.
N.A.
2.
Power Range, Neutron Flux a.
High Setpoint s109% of RTP*
5110.9% of RTP*
b.
Low Setpoint 525% of RTP*
s27.1% of RTP*
3.
Power Range, Neutron Flux, s5% of RTP* with a 56.3% of RTP* with High Positive Rate time constant a time constant 2 2 seconds a 2 seconds 4.
Intermediate Range, Neutron Flux s25% of RTP*
s31% of RTP*
5 5
5.
Source Range, Neutron Flux s10 cps s1.4 x 10 cps 6.
Overtemperature AT See Note 1 See Note 2 7.
Overpower AT See Note 3 See Note 4 8.
Pressurizer Pressure-Low 21945 psig 21938 psig***
9.
Pressurizer Pressure-High s2385 psig 52399 psig
{
10.
Pressurizer Water Level-High 592% of instrument span s93.8% of instrument span o
i 11.
Reactor Coolant Flow-Low 290% of loop minimum 288.9% of loop minimum measured flow **
measured flow **
o E
- RTP = RATED THERMAL POWER l
- Loop minimum measured flow = 95,500 gpm
- Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 2 seconds for lead and 1 second for lag. Channel calibration shall ensure that these time constants are adjusted to these values.
UNIT 2 ONLY TABLE 2.2-1 9
3;!
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
!!i*
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE i
E 1.
Manual Reactor Trip N.A.
N.A.
Z 2.
Power Range, Neutron Flux
~
a.
High Setpoint s109% of RTP*
s110.9% of RTP*
b.
Low Setpoint 525% of RTP*
s27.1% of RTP*
3.
Power Range, Neutron Flux, 55% of RTP* with a s6.3% of RTP* with High Positive Rate time constant a time constant a 2 seconds a 2 seconds 4.
Intermediate Range, Neutron Flux 525% of RTP*
s31% of RTP*
m 6
5 4,
5.
Source Range, Neutron Flux s10 cps sl.4 x 10 cps
=
6.
Overtemperature AT See Note 1 See Note 2 7.
Overpower AT See Note 3 See Note 4 8.
Pressurizer Pressure-Low 21945 psig 21938 psig***
9.
Pressurizer Pressure-High 52385 psig 52399 psig y
10.
Pressurizer Water Level-High 592% of instrument span s93.8% of instrument span 11.
Reactor Coolant Flow-Low 290% of loop minimum 288.9% of loop minimum g
measured flow **
measured flow **
l E
t a
- RTP = RATED THERMAL POWER S
- Loop minimum measured flow = 96,250 gpm
- Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 2 seconds for lead and I second for lag. Channel calibration shall ensure that.these time constants are adjusted to these values.
UNIT 1 ON(.Y TABLE 2.2-1 (Continued) n D
TABLE NOTATIONS Ey NOTE 1: OVERTEMPERATURE AT i
AT (1 + r S) (
1
)
s AT, { K - K, ( 1 + r,5 ) [ T (
1
) - I'] + K (P - P') - f (AI))
c-i i
3 t
5 (1 + 7 5) (1 + T S)
(1 + r S)
( 1 + T, ".)
3 s
Measured AT by Loop Narrow Range RTDs; Where: AT
~
=
Lead-lag compensator on measured AT; 1+75 3
1+T52 Time constants utilized in lead-lag compensator for AT, r - 12 s, T,
7
=
i 2
i r = 3 s; p
Lag compensator on measured AT; 1
=
1+TS3 Time constants utilized in the lag compensator for AT, r = 0;
?>
r 3
3 D
AT, Indicated AT at RATED THERMAL POWER;
=
1.1954 l
K
=
i 0.03371/ F l
K
=
g The function generated by the lead-lag compensator for T,y 1 + r.S 1+TS dynamic compensation; 3
k Time constants utilized in the lead-lag compensator for T,y, T
22 s, T, r
=
=
4 3
4 T3-4 s; 3
Average temperature, F;
g T
=
2 Lag compensator on measured T,y; P
1
=
l+rSs Time constant utilized in the me,asured T,y lag compensator, 73= 0; r
=
s k
--- -.--.----.----------e-.
r,------
-+-a
-w
-~rc---w
-ss, y
.~,
-v 4
-s------~
UNIT 2 ONLY TABLE 2.2-1 (Continued) 9g TABLE NOTATIONS c
E NOTE 1: OVERTEMPERATURE AT i
. g AT (1 + T 5) (
1
)
s AT,, (K
-K (1 + T 5) [T (
1
) - T'] + K (P - P') - f (61))
3 i
2 3
3 i
q (1 + T 5) (1 + T 5)
(1 + r S)
(1 + r S) 2 3
s s
~
Where: AT Measured AT by Loop Narrow Range RTDs;
=
I+rS lead-lag compensator on measured AT;
=
i 1+TS2 Time constants utilized in lead-lag compensator for AT, r = 12 s, r,T
=
i 2
i r = 3 s; 2
1 Lag compensator on measured AT;
=
1+TS3 "g
Time constants utilized in the lag compensator for AT, r = 0; T
=
3 3
AT Indicated AT at RATED THERMAL POWER;
=
o 1.1953 K
=
i i
0.03163/ F
=
k 1 + T,S The function generated by the lead-lag compensator for T,y o
=
k 1+rS dynamic compensation; s
o#
Time constants utilized in the lead-lag compensator for T,y, 7
22 s, T,
Ts
=
=
4 4
,8 r = 4 s; s
T Average temperature, F;
=
Lag compensator on measured T,y; 1
=
I + r,,S Time constant utilized in the me,asured T,y lag compensator, r = 0; r
=
3 s
.w..
m r
v
,m.--
_,w<
~v.-
,,.m,,.
y-
UNIT 1 ONLY TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued)
[
NOTE 1:
(Continued) z T' s 590.8*F (Nominal T, allowed by Safety Analysis);
0.001529; l
K 3
Pressurizer pressure, psig; P
P' - 2235 psig (Nominal RCS operating pressure);
Laplace transform operator, s;
S and f (AI) is a function of the indicated difference between top and bottom detectors of the power-3 range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that:
m (1)
For q, - q, between -42.0% and +8.0%,
l f (al) - 0, where qt and qs are percent RATED THERMAL POWER in the top and bottom halves of 3the core respectively, and q, + qu is total THERMAL POWER in percent of RATED THERMAL POWER;
- q is more negative than -42.0%, the AT Trip For each percent AI that the magnitude of q$.6725 of AT,; and (ii)
Setpoint shall be automatically reduced by W
(iii)
For each percent Al that the magnitude of q - q is more positive than +8.0%, the AT Trip a
Setpoint shall be automatically reduced by I.640$ of AT,.
5 5
NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more h
than 4.5% of Rated Thermal Power.
l w
e
,.. _ - - -. _. _ -. _ ___. _~---_
- n-- - u
,w-
UNIT 2 ONLY TABLE 2.2-1 (Continued) g TABLE NOTATIONS (Continued)
NOTE 1:
(Continued) z T' s 590.8'F (Nominal T allowed by Safety Analysis);
y K
0.001414;
=
3 P
Pressurizer pressure, psig;
=
P' = 2235 psig (Nominal RCS operating pressure);
Laplace transform operator, sd; S
=
and f (AI) is a function of the indicated difference between top and bottom detectors of the power-3 range neutron ion chambers; with gains to be selected based on measured instrument response during y
plant STARTUP tests such that:
8 (i)
For q, - q, beNeen -M.% ad 4.M, f (AI) = 0, where qt and q, are percent RATED THERMAL POWER in the top and bottom halves of 3
the core respectively, and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER; (ii)
For each percent AI that the magnitude of q - q i s more negative than -39.9%, the AT Trip Setpoint shall be automatically reduced by $.9101 of AT,; and (iii)
For each percent AI that the magnitude of g - q i s more positive than +3.0%, the AT Trip f
Setpoint shall be automatically reduced by k.3161 of AT,.
a 55 NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 4.5% of Rated Thermal Power.
l 6
t
~
6
..=.mm s
m u
,_r e
.' +
.a-
E]IT 1 ONLY TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued)
SE NOTE 3: OVERPOWER AT s
s; AT (1 + rdS) (
1
) s AT {K -Ks(
r,S
)(
1
) T - K [T (
1
) - T"] - f (AI)}
o 4
2 (1 + 7 S) (1 + T 5)
(1 + T S) (1 + T 5)
(1 + 7,S) 7 3
7 6
Where: AT As defined in Note 1,
=
As defined in Note 1, 1 + rdS)
=
1 + r:S As defined in Note 1,
.ri, 77
=
As defined in Note 1, 1
=
1+TS3
}'
As defined in Note 1, r
=
3 e
AT As defined in Note 1,
=
o 1.0855 l
K
=
4 0.02/ F for increasing average temperature and 0 for decreasing average K
=
s temperature, The function generated by the rate-lag controller for T,y dynamic r,S
=
27 1 + r,S compensation, e'
Time constant utilized in the rate-lag controller for T,,,,, r, = 10 s, T,
=
5 1
As defined in Note 1,
=
1+rSs As defined in Note 1, T
=
6 w
i,,.
MMD
=
.- a
. a.
. m.
m m
e--
a w
4 7**'--
9
E]IT 2 DNLY TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued)
S3 NOTE 3: OVERPOWER AT-i gg AT (1 + r S) (
1
) s AT, { K
-K
(
r,S )(
1
)T-Ks [T (
1
) - T"] - f (AI)}
i 4
3 z
(1 + 7 5) (1 + T S)
(1 + T S) (1 + r,,5)
(1 + T 5) g 7
3 f
3
~
Where: AT As defined in Note 1,
=
1 + r S)
As defined in Note 1,
=
i 1+rSp As defined in Note 1, r,72
=
i 1
As defined in Note 1,
=
1+TS3 3
As defined in Note 1, T
=
3 e
AT, As defined in Note 1,
=
1.0819 l
K.
=
0.02/ F for increasing average temperature and 0 for decreasing average K
=
s temperature, The function generated by the rate-lag controller for T,y dynamic r7S
=
gp 1+TS compensation, f
m Eh Time constant utilized in the rate-lag controller for T,y, r7 = 10 s, 7
=
7 6
5 1
As defined in Note 1,
=
g 1+TS As defined in Note 1, 7
=
3 S
h m -.
a-. m. : -
. -. m um m
m r
a
=
w
-1.
.m e-
.v-*.
UNIT 1 DNLY TABLE _2.2-1 (Continued) b!
E TABLE NOTATIONS (Continued)
SE NOTE 3:
(Continued)
I 0 for T s 590.8 F, l
0.001262/ F for T > 590.8 F and K c:
K
=
=
3 3
5
-d As defined in Note 1, T
=
Indicated T,y at RATED THERMAL POWER (Calibration temperature for AT T"
=
instrumentation, s 590.8 F),
As defined in Note 1, S
=
and f (AI) is a function of the indicated differences between top and bottom detectors 7
of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
for q, - qt, between 35% and +35% AI; f, THERMAL POWER in the top and bottom halv(AI) = 0, where qt and q3 are percent RATED (i) es of the core respectively, and qt + q3 is 4,;;
total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent Al that the magnitude of qt - q3 is more negative than -35% AI, the AT Trip Setpoint shall be automatically reduced by 7.0% of AT,; and (iii) for each percent AI that magnitude of q, - q3 is more positive than +35% AI. the AT Trip Setpoint shall be automatically reduced by 7.0% of ATg 2n NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more 3
than 3.0% Rated Thermal Power.
l n
F w
M
EDIT 2 DNLY TABLE 2.2-1 (Continued) n 3%3 TABLE NOTATIONS (Continued)
EE NOTE 3:
(Continued) 0.001291/"F for T > 590.8 F and Ks = 0 for T s 590.8"F, gg K
=
s
[l T
As defined in Note 1,
=
Indicated T,, at RATED THERMAL POWER (Calibration temperature for AT T"
=
instrumentation, s 590.8 F),
As defined in Note 1, S
=
and f (AI) is a function of the indicated differences between top and bottom detectors 2
of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) for qt - qs between - 35% and +35% AI; f. (AI) = 0, where qt and qt, are percent RATED n,
d, THERMAL POWER ir
- s top and bottom haIves of the core respectively, and qt + 40 is Es total THERHAL POWER in percent of RATED THERMAL POWER; (ii) for each percent Al that the magnitude of qt - 43 is mere negative than -35% AI, the AT Trip setpoint shall be automatically reduced by 7.0% of AT ; and o
(iii) for each percent AI that magnitude of q, - q3 is more positive than +35% AI, the AT Trip Setpoint shall re automatically reduced by 7.0% of AT.
o gp NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more g
than 3.3% of Rated Thermal Power.
l Q-an O
".a S
.N l
.R
4 UNIT 1 ONI.Y 1
385,820 a s, an y sr 0.n f or.no4 i < t ec p
' s.4 = 4 4,f v edtM i:M,MQ G od 4 e a su oment s c e< t aet y o f 2.* % t u CCof auon ow at e a:uo+c n :nis riqu e.
A gggen 382,000
,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,( 9 8 ; 3 8 2, 000 )
I Restrictec
'5378,180_
Operation
( 9(>. 3 7 A,180) 5; Regien n
2 m
i b374,360 (94.374,360) c-E o
~
~
)
i e,n 1
(92.370,540)
I j
c 370,540.:,
2 O
Oo Prohibited 2
Oper ation u
S366,720 (90.366,720)
Region C. "
}
362,900 i
359,080 86 85 90 92 94 96 98 10 0
'02 Fraction of Rated Thermal Power Tigure 3.2-1 Reactor Coolant System Total Flow Rate Versus Rated Thermal Power Four Loops in Operation CATAWBA UNIT 1 3/4 A2 16 Amen &;aent No.113
p
^
UNIT 2 ONLY l
388850 a a e an s a t 0..n t or ' nse e e<;1 *a
- e.g. a t u. maurt s -w eg and a p
e a su stnant r.c w e a ney of 2.* % f or CC ef ation
- o. ar e ncuo.o a as nc.s.
R agicn 3 8 5 0 0 0 - - -- ---. - -..........................,------ - -........t 9 a.J a 5 o co n 9
Restricted E 381150 -
Operation (96.sstisci c.
i 3
Regen 3
E Ec S 377300-
- 3773001 t:
E 2
m
\\
i C/3 h373450 U '* * **I o
C I
O 3
Prohibited
~
'G Operation
$ 3656c0-
" #8'8 "3 Region j
I l
1 I
365750 t
l 3611:00 86 88 90 92 94 96 98 m
tog Fraction of Rated Thermal Power l
I Figure 3.2 1 Reactor Coolant System Total Flow Rate Ver sus Rated Thermal Power Four Loops in Operation CATAWBA UNIT 2 3/4 B2 16
' Amendment No. 107 a