ML20083R129
| ML20083R129 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/05/1995 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17352B147 | List: |
| References | |
| NUDOCS 9505260377 | |
| Download: ML20083R129 (18) | |
Text
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ATTACEMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked up Technical Specification Pages; 2-2 ,
2-4 2-5 2-1 2-8 2-9 2-10 3/4 2-16 -
3/4 3-24 3/4 3-26 3/4 3-27 '
3/4 3-30 B 3/4 2-8 9505260377 950505 PDR ADOCK 05000250 P PDR
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. 1 FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT - THREE LOOPS IN OPERATION TURKEY POINT - UNITS 3 & 4 2-2 AMENDHENT N05.137AND I32 1
It45 G R T A 670 660 45gpgg UNACCEPTABLE OPERAT10N
" uoo esa 640 N.
,E _ co PSW F 620 4 l 610 ****- '
600 590 - Acca m s u _
OPERATION 1
580 3
0.1 0.20.30.40.50.60.70.80.9 1 1.1 1.2 POWER (FRACTION OF NOMINAL) l Figure 2.1-1 ,
Reactor Core Safety Limit - Three Loops in Operation 1
g TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUNENTATION TRIP SETPOINTS a
g FUNCTIONAL UNIT ALLOWANCE (TA) Z S TRIP SETPOINT ALLOWA8LE VALUE l
- 1. Manual Reactor Trip N.A N.A N.A N.A. N.A.
E q 2. Pouer Range, Neutron Flux
- a. High Setpoint 7.5 4.56 0.0 1109% of RTP** 1112.0% of RTP**
- b. Law Setpoint 8.3 4.56 0.0 125% of RTP**' 128.0% of RTP**
- 3. Intermediate Range, 13.5 8.41 0.0 Neutron Flux -(25% of RTP** -
<31.0% of RTP**
32
- 4. Source Range, Neutron Flux 13.9 10.01 0.0 1105 cps <1.4 x 105 cps
- 5. Overtemperature AT h 4:9 58 See Note 1 See Note 2
- 6. Overpouer AT 5-5 sd 2.0 See Note 3 See Note 4 ,
- 7. Pressurizer Pressure-Low 4.5 34 1.12 1.4 >1835 psig >1817 psig i
- 8. Pressurizer Pressure-High 5.5 1.12 1.4 12385 psig
, 12403 psig
- 9. Pressurizer Water Level-High 8.0 6.8 4.0 <92% of instriment <92.2% of in trument .
l g3 p Span ipan gg,g l 10. Reactor Coolant Flow-Low 4.6 t-7 ed >90% of I > E% of loop ilesign f aeiTgn f1 l 11. Steam Generator Water Level 5.0 t35 M to 89
> o rrow > of na i
g low-Lou g r instrument range instrument p span span p
- * > design flow = 89,500 gpa g
- Loo *RT* = Rated Thermal Pouer l'
- 82.0% span for AT (RTDs) t G.5% for pressurizer pressure' I
I k
g TABLE 2.2-1 (Continued) 2.
g REACTOR TRIP SYSTEN INSTRUENTATION TRIP SETPOINTS i
3 '
g FUNCTIONAL UNIT ALLOWANCE (TA) Z S TRIP SETPOINT ALLOWA8LE VALUE
- 12. Steam /Feedwater Flow 20.0 3.67 - 7. 3" Feed Flow <20%
g Mismatch below steai flow Feed Flow <23.9%
a below steai flow g Coincident With
- og f.17 g,9 oj, w Steam Generator Water 5.0 33- la > of narrow. > . iof narrow
- Level-Low ,
l r age instrument range instrument '
span span
- 13. Undervoltage - 4.16 kV 20.0 1.12 0. 0 >70K bus voltage ->695 bus voltage Susses A and B t
- 14. Underfrequency - Trip of Reactor 6.5 0.03 0. 0 ->56.1 Hz >55.9 Hz Coolant Puup 3reaker(s) Open -
u E 15. Turbine Trip '
l a. Auto Step 011 Pressure 2.6 1.0 0. 0 >45 psig >42 psig ;
- b. Turbine Step Valve Closure N.A. N.A. N.A. Fully Closed *** Fully closed ***
i
- 16. Safety Injection Input from ESF N.A.- N.A. N.A. N.A. N.A. ;
g 17. Reactor Trip System Interlocks ;
g a. Intermediate Range N. A. N.A. N.A. Nominal 1x10 18 amp ->6.0x10 11 amps g Neutron Flux, P-6 v.
" e
. *** Limit switch is set when Turbine Stop Valves are fully closed.
E "1.7% span for staan line flow, 2.9K span for feedwater flow and 2.8K span for steam line pressure. i B
N
s.
G:=
5 TABLE 2.2-1 (Continued) 3 TABLE NOTATIONS y NOTE 1: OVERTEMPERATURE AT
[m AT f I + r iS ( 1
) 5 ATo (Ki-K2 f I + r es)
[I+rS ( 1 + rsS) [T ( 1+r5 ) - T'] + K3 (P - P') - fi (AI)}
1 2 1+rS3 3 5 w l#iere: AT = Measured AT by RTD Instrumentation 1+rSi =
lead / Lag compensator on measured AT; ir =0s, r2 -Os I+T32 1 =
Lag compensator on measured AT; T3=h
- I+TS3 ATo =
Indicated AT at RATED THERNAL POWER Ki = t 09'J; I'25
$ K2 = 0.0107/ F; O.01 6 ,-
1 + 7 45_ =
The function generated by the lead-lag compensator for T ,,,
I+TSS dynamic compensation; T,r5 4
=
Time constants utilized in the lead-lag compensator for T,,g,'r4 - 25s, g 75 - 3 s; T = Averaletemperature,8F; z
]g 1 1+rSs Lag compensator on measured T,,g; rs"h y T' ' s 574.2 F (Nominal T,, at RATED THERNAL POWER);
g K
3
= 0.=dsig; o. oo t l P = Pressurizer pressure, psig;
g TABLE 2.2-1 (Continued) g TABLE NOTATIONS (Continued)
NOTE 1: (Continued) 3 P' 1 2235 psig (Nominal RCS operating pressure); l S =
Laplace transform operator, s 1; 1 ~
g and fa (AI) is a function of the indicated difference between top and bottom detectors of the power range neutron ion chambers; with gains to be selected based on measured instrument l
,, response during plant startup tests such d (1) For q g g between W Jand M , fa (AI) = 0, where gg and qb are percent RATED THERMAL POER in the top and bottom halves of the core respectivel qg + g is total THE N PO E R in percent of RATED THENt4L POWER; -%%
(2) For each percent that the magnitude of g t ~9b exceeds [IK the AT Trip Setpoint shall ,
y be automatically reduced by 1.5% of its value at RATED THERMAL POWER; and a,
-- +2% o (3) For each percent that the magn 1 M of gg g exceeds L: 10,[the AT Trip Setpo nt shall be automatically reduced by 4.% ef its value at RATED THERMAL POWER.
2.3 %
- g NOTE 2
- The channels maximum trip setpoint sha m not exceed its computed setpoint by more than W of instr oent span. ' .
i o.73*4 m
E b
CPb i
R
g
- TABLE 2.2-1 (Continued) 5 .
_ TABLE NOTATIONS (Continued) 3 NOTE 3: OVERPOWER AT AT ,'1 + tis 1 ( 1 3 i AT (K4 -K 5 I S II-- I I T-K I I g L1 + 1 5J (1 + t:5D o 1 + trS * [T I - T"] - f a (AI)}
(1 + TsS) (1 + taS)
Q nihere: AT =
- As defined in Note 1 4,
1 + tis =
As defined in Note 1, 1 + tas 1 =
As defined in Note 1 1 + ta5 l
AT, = As defined in Note 1, I K.
Ks sus.@ -
I
> 0.02/*F for increasing average temperature and 0 for decreasing average tosperature, l I2
$ 3,fy5 =
funct on compensation, prated h tk ratring cesaur for T,,, @namic ty =
5 Time constants utilized in the rate-lag compensator for 1 =
T,,,, t, > 10 s, ! .
1 . ,,, As .efined in . te 1 O
b m
c.e e
y TA8LE 2.2-1 (Continued) j TA8LE NOTATIONS (Continued) i
- o.co232
$ NOTE 3: (Continued)
'i Ks =
4:4006af*F for T > T" - i g = 0 for T S T", l 3 T = As defined in Note 1, '
w
,, T" =
Indicated T , at RATED THERMAL POWER (Calibration temperature for AT l instrumentation, 1 574.2*F),
S = As defined in Note 1, and fs (AI) = 0 for all AI '
3 o
NOTE 4: The l's maximum trip setpoint shall not exceed its computed trip setpoint by more than . of instrument span.
0.4 5
1 5
w i i
8
. I
POWER OISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS .
LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the-following limits;
- a. Reactor Coolant System T avg 5,576.6*F
- b. Pressurizer Pressure > 2209 psig*, and
- c. Reactor Coolant System Flow >277,900 gpm APPLICABILITY: MODE 1.
ACTION:
With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% 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 />.
SURVEILLANCE REQUIREMENTS ,7 N (145 E RAT W HRM
- 4.2.5.1l E;-h
,2_2 _ _.
o,_f__.the p r x te,r; ;he.;n ebewe shell b; se,-ified te be within lm_
4.2 M The RCS flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.
h , .-......IS ITh; "CS f1:u r;t; :h:li be d; ;a;;reted by x::: :x t ::::per 18 N
(NS6R.T (C.) N6?.E ~
J
- Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.
i TURKEY POINT - UNITS 3 & 4 3/4 2-16 AMEN 0 MENT N05.137 AND 132
g TABLE 3.3-3 (Continued) ;
ENGINEERED SAFETY FEATURES ACTUATION SYSTEN IN5IRURtNIATION TRIP StIPOINIS 3
~
E TRIP -
, FUNCTIONAL UNIT ALLOWANCE (TA) _Z _S SETPOINT ALLOWABLE VALUE#
E Coincident with: 13.0 1.16 2.3 1614 psig 1588 psig !
~.; Steam Generator I
- Pressure--Low ;
avg--Low '4.0 T f:0 , 1. 0
, 1543*F 1542.5'F
- a. Automatic Actuation Logic N.A N.A N.A N.A. M.A.
and Actuation Relays
$ b. Containment Pressure--Nigh-Nigh Cetacident with:
21.3 2.7 0.0 120.0 psig 122.6 psig A Containment Pressure--Nigh 13.3 10.3 0.0 1 4.0 psig i 4.5 psig
- 3. Containment Isolation
- a. Phase "A" Isolation
- 1) Hanual Initiation N.A- ,N.A. N.A. N.A. N.A.
- 2) Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Relays g 3) Safety Injection see item 1 See Item 1 above for all Safety
,e Injection Trip Setpoints and
- Allowable Values.
A
- b. Phase "B" Iso 15 tion B
- 1) Manual In1tIation N.A. N.A. N.A. N.A. N.A.
I %
l TABLE 3.3-3 (Continued)
N ENGINEEP.ED SAFETY FEATURES ACTUATION SYSTEM
@ INSTRUMENTATION TRIP SETPOINTS 3
TRIP
@ FUNCTIONAL UNIT ALLOWANCE fTA1 Z S SETPOINT ALLOWABLE VALUE#
- 4. Steam Line Isolation (Continued)
E U b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
[ and Actuation Relays
- c. Containment Pressure-High- 21.3 2.7 0.0 s20.0 psig High Coincident with: 522.6 psig Containment Pressure-High 13.3 10.3 0.0 54.0 psig $4.5 psig ,
, d. Steam Line Flow-High 16.7 2.86 3.9 l sA function defined SA function defined as follows: A op as follows: A ap corresponding to corresponding to u 40% steam flow at 42.6% steam flow at
) 0% load increasing 0% load increasing u
linearly from 20% linearly from 20%
eb load to a value load to a value i
- corresponding to corresponding to 120% steam flow 122.6% steam flow at full Icad. at full load.
Coincident with 13.0 1.16 2.3 2614 psig 2588 psig Steam Line Pressure-Low 2,I h or , ,
g T ,--Low 4.0 -Ed 1.0 1543*F 2542.5'F
- 5. Feedwater Isolation g a. Automatic Actuation Logic N.A. N.A. N.A. N.A. .N.A.
, and Actuat,lon Relays
- b. Safety Injection see item 1 See Item 1. above for all Safety l
2: Injection Trip Setpoints and O Allowable Values.
- c. Steam Generator Water Level 20.0 18.27 2.0 580% of narrow 581.9% of narrow High-High range instrument range instrument span. span.
4 l
TABLL a (Continued) -
- ENGINEERED SAFETY FEATURES ACTUATION SYSTEM 3
! IN5HRstNIAIION IRIP RIPUINIS 4 b TRIP i g FUNCTIONAL UNIT ALLOWANCE (TA) Z S SETPOINT ALLOWABLE VALUEA
- 6. Auxiliary Feeduster (3) g a. Automatic Actuation Logic N.A. N.A. N. . N.A N.A.
g and Actuation Relays . 2.0 t o */o 189%
w b. Steam Generator hinter Level--Low-Low 5.0 33 9
- 1 of narrow range instrument M of narrow range instrument l
- span. span.
- c. Safety Injection see item 1 See Item 1. above for all Safety i InjectionTripSetpointsandA110weble '
Values.
$ d. Bus Stripping . see item 7 See Item 7. below for all Bus Stripping Trip Setpoints and Allowable 4 Values. i w
- e. Trip ef All Main Feeduster N.A. N.A. N.A. N.A. M.A.
Pimp Breakers ,
i
- 7. Loss of Power
- a. 4.16 kV Busses A and B N.A. N.A. N.A. N.A. N.A. I (Loss of Voltage) g ,
h 5
5 e i i "s
R -
TABLE 3.3-3 (Continued)
R ENGINEERED SAFETY FEATURES ACTUATION SYSTEM Q IN5IRUrtNIATION TRIP SLIPOINIS
~
3 TRIP 5 FUNCTIONAL UNIT ALLOW 4NCE (TA) S SETPOINT
. Z_ ALLOWABLE VALUEi c8 Engineering Safety Features
% . Actuation System Interlocks i m w a. Pressurizer Pressure N.A. M.A. N.A. Nominal 2000 psig '
! ** 12018 psig
.* b.
L\ --
T ,,--Low 4.0 -2:t 1.0 Nominal 543*F 1542.5'F
- 9. Control Room Ventilation Isolation
- a. Automatic Actuation i
y logic and Actuation Relays N.A. M.A. N.A. N.A. M.A.
Y b. Safety Injection see item 1 See Item 1. above for all Safety M Injection Trip Setpoints and Allowable Values.
- c. Containment Radioactivity-- N.A. N.A. N.A.
High (1) Particulate (R-11) Particulate (R-11)
<6.1 x 105 CPM <6.8 x 105 CPM Caseous (R-12) Caseous (R-12)
See (2) See (2) k d. Containment Isolation N.A. N.A. N.A. N.A. N.A.
5 Manual Phase A or Manual g Phase 8
- e. Air Intake Radiation Level N.A. M.A. N.A. 5 2 mR/hr 1 2.83 mR/hr t
g TABLE NOTATIONS 3(1) Either the particulate or gaseous channel in the OPERABLE status will satisfy this LCO.
' I l
POWER DISTRIBUTION LIMITS BASES 3/4.2.4 00ADRANT POWER TILT RATIO ;
The QUADRANT POWER TILT RATIO limit assures that the radial power dis-tribution satisfies the design values used in the power capability analysis.
Radial power distribution measurements are made during STARTUP testing and periodically during power operation.
The limit of 1.02, at which corrective action is required, provides DNB .
and linear heat generation rate protection with x y plane power tilts.' A limit of 1.02 was selected to provide an allowance for the uncertainty asso-ciated with the indicated power tilt. .
The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correc-tion of a dropped or misaligned control rod. In the event such action action does not correct the tilt, the margin for uncertainty on Fq (Z) is reinstated by reducing the maximum allowed power by 3% for each percent of tilt in excess ,
of 1.
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors or incore thermocouple map are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles.
The two sets of four symmetric thimbles is a unique set of eight detector
3/4.2.5 DNS PARAMETERS The limits on the DNS-related parameters assure that each of the param- i eters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated ade- ,
quate to maintain a minimus DN8R above the applicable desig'n limits throughout each analyzed transient. The indicated T,,, value of 576.6 F and the indicated pressurizer pressure value of 2209 psig correspond to analytical limits of 578.2*F and 2185 psig respectively, w th allowance for measurement uncertainty.
Q The indicated RCS flow value of 277,900 gpm corresponds to an analytical '
@I limit of 268,500 gpa which is assumed to have a 3.5% measurement unceptainty.
The above measurement uncertainty estimates assume that these instrument channel outputs are averaged to minimize the uncertainty.
3 The 12-hour periodic surveillance of these parameters through instrument b readout is sufficient to ensure that the parameters are restored within their d limits following load changes and other expected transient operation.l W
m <
2 TURKEY POINT - UNITS 3 & 4 B 3/4 2-8 AMENDMENT N05137 AND132
_ _ _ _ .~ r vr- n r v,, .w - -r n-,-, * - - , v
'w l o *
~
INSERT (B) t Reactor Coolant System T,, and Pressurizer Pressure shallper once be12verified hours. to be within their limits at least 4.2.5.2 RCS flow rate shall be monitored for degradation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
rusERT fc)
After each months, fuel loading, and at least once per 18 the RCS flow rate shall be determined by precision heat balance after exceeding 90% RATED THERMAL POWER. t The measurement instrumentation shall be calibrated within 90 days prior to the performance of the calorimetric flow measurement. The provisions of 4.0.4 are not applicable for performing the precision heat balance flow measurement. '
INSERT (D)
The 18-month periodic measurement of the RCS to\al flow rate is adequate to ensure that the DNB-related flow assumption is met and to ensure measured flow. correlation of the flow indication channels with <
Six month drift effects have been included for !
feedwater temperature, feedwater flow, steam pressure, and the pressurizer pressure inputs. The flow measurement is performed within ninety days of completing the cross-calibration of the hot surveillance on a 12-hour basis will provide sufficient verification that flow degradation has not occurred. A change in indicated percent flow which is greater that the instrument channel inaccuracies and parallax errors is an appropriate indication on RCS flow degradation. '
. . . , y ._.._ . _ - . . . . . , _
KTTAQHMENT 4 PROPRIETARY WCAP 13719, REV. 1 WESTINGHOUSE REVISED THERM 3LL DESIGN PROCEDURE INSTRUMENT UNCERTAINTY METHODOLOGY and NON-PROPRIETARY WCAP 13718, REV. 1 NESTINGEOUSE REVISED THERMAL DESIGN PROCEDURE INSTRUMENT UNCERTAINTY METHODOLOGY i
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