ML17352B184
| ML17352B184 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/23/1995 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17352B183 | List: |
| References | |
| NUDOCS 9505310100 | |
| Download: ML17352B184 (26) | |
Text
ATTACHMENT 3 PROPOSED LICENSE AMENDMENT FOR IMPLEMENTATION OF A CHANGED COLUMN FORMAT FOR RPS AND ESFAS TECHNICAL SPECIFICATION SETPOZNTS PROPOSED TECHNICAL SPECIFICATIONS 2-3 2-4 2-5 2-6 B 2-3 B 2-3a 3/4 3-13 3/4 3-23 3/4 3-24 3/4 3-25 3/4 3-26 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-30 3/4 3-31 B 3/4 3-1 B 3/4 3-1a 9505310100 950523 PDR ADOCK 05000250
~ P...'DR
SAFETY LIHITS AND LIHITING SAFETY SYSTEH SETTINGS 2.2 LIHITING SAFETY SYST H SETTINGS REACTOR TRIP SYSTEH INSTRUHENTATION SETPOINTS 2.2.)
The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
~APII Ahli I A
- h I
h h
I I
T hi 3.3-1.
Action:
a ~
Mith a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the setpoint consistent with the Trip Setpoint value within the permissible calibration tolerance.
b.
Mith the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Value column of Table 2.2-1, either:
Adjust the Setpoint consistent with the Trip Setpoint value of T Ai 2 2 I d d t I
Itht 12 h
- th
~23:.",:BFA."224422 5
aqm%tD>>
5?BNBM~o..
2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3. 1 until the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.
TURKEY POINT - UNITS 3 5 4 2-3 AHENDMENT NOS.
AND
. ~
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT ALLOWABLE VALUE TRIP SETPOINT 1.
Power Range, Neutron Flux a.
High Setpoint b.
Low Setpoint 3.
Intermediate
- Range, Neutron Flux N.A
<112.04 of RTP**
<28.04 of RTP**
<31.0% of RTP**
N.A.
<109% of RTP**
<254 of RTP**
<254'f RTP**
4.
Source
- Range, Neutron Flux
<1.4 X 10 cps
<10 cps 5.
Overtemperature hT See Note 2
See Note 1
6.
Overpower hT 7,,
Pressurizer Pressure-Low 8.
Pressurizer Pressure-High 9.
Pressurizer Water Level-High See Note 4
>1817 psig
<2403 psig
<92.24 of instrument span See Note 3
>1835 psig
<2385 psig
<92% of instrument span 10.
Reactor Coolant Flow-Low ll. Steam Generator Water Level Low-Low
>88.74 of loop design flow*
>13.24 of narrow range instrument span
>90% of loop design flow*
>15% of narrow range instrument span
- Loop design flow = 89,500 gpm
- RTP = Rated Thermal Power
0H I
g FUNCTIONAL UNIT 12.
Steam/Feedwater Flow Mismatch Coincident With Steam Generator Water Level-Low TABLE 2.2-Conti ued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS ALLOWABLE VALUE Feed Flow <23.PA below Steam Flow
>13.2X of narrow range instrument span TRIP SETPOINT Feed Flow <2N below Steam Flow
>15% of narrow range instrument span a
W 0
13.
- 4.16 kV Busses A and B
14.
Underfrequency
- Trip of Reactor Coolant Pump=Breaker (s)
Open 15.
Turbine Tr ip a.
Auto Stop Oil Pressure b.
Turbine Stop Valve Closure 16.
Safety Injection Input from ESF 17.
Reactor Trip System Interlocks a.
Intermediate Range Neutron Flux, P-6
>6PA bus voltage
>55.9 Hz
>42 psig Fully Closed***
N. A.
>6.0x10 amps
>7Ã bus voltage
>56.1 Hz
>45 psig Fully Closed~*
N.A.
Nominal 1x10" amp
- Limit switch is set when Turbine Stop Valves are fully closed.
FUNCTIONAL UNIT TABLE 2.2-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS ALLOWABLE VALUE TRIP SETPOINT b.
Low Power Reactor Trips Block, P-7 1)
P-10 input 2)
Turbine First Stage Pressure c.
Power Range Neutron Flux, P-8 d.
Power Range Neutron Flux, P-10 18.
Reactor Coolant Pump Breaker Position Trip 19.
Reactor Trip Breakers
-20.
Automatic Trip and Interlock Logic
<13.No RTP**
<13.N Turbine Power
<48.Nl RTP**
>7.0% RTP**
N.A.
N.A.
N.A, Nominal IN of RTP"*
Nominal 1% Turbine Power Nominal 45K of RTP**
Nominal 10%%u of RTP**
N.A.
N.A.
N.A.
- RTP RATED THERMAL POWER
~.2 LIMITING SAFETY S
M SETTINGS BASES 2.2.1 REACTOR TRIP S
STE INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the nominal values at which the Reactor trips are set for each functional unit.
The Trip Setpoints have been selected to ensure that the core and Reactor Coolant System are prevented from exceeding their safety limits during normal operation and design basis anticipated operational occurrences and to assist the Engineered Safety Features Actuation System in mitigating the consequences of accidents.
The setpoint for a reactor trip system or interlock function is considered to be adjusted consistent with the nominal value when the "as measured" setpoint is within the band allowed for calibration accuracy.
The methodology to derive the Trip Setpoints includes an allowance for instrument uncertainties.
Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties.
Sensor and other instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes.
TURKEY POINT UNITS 3
& 4 B 2-3 AMENDMENT NOS.
AND
2.2 LIMIT G
AFETY S STEM SETTINGS BASES The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a
pres'et or calculated level.
In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity.
The functional capability at the specified trip setting is required for those. anticipatory or diverse Reactor trips for which no direct credit was assumed in the safety analysis to enhance the overall reliability of the Reactor Trip System.
The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated.
This prevents the reactivity insertion that would otherwise result from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.
Manual Reacto Tr The Reactor Trip System includes manual Reactor trip capability.
TURKEY POINT - UNITS 3 8L 4 B 2-3a AMENDMENT NOS.
AND
INSTRUMENTA IO 3 4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION e
ng neere a
e y ea ure c ua on ys em sns rumentation channels and interlocks shown in Table 3.3-2 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-3.
L~PPLI IIPILI:
3 3
I I 31 3.3.2, ACTION:
a.
Mith an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-3, adjust the setpoint consistent with the Trip Setpoint value within the permissible calibration tolerance.
b.
lfith an ESFAS Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Value column of Table 3.3-3, either:
Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-3 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Q~e:;affieeQ
'han t%e~4FfN%~a'.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Table 3.3.2 until the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.
- c. Mith an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-2.
SURVEILLANCE RE UIREMENTS ac ns rumen a ion c anne an sn er oc an e au omatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
TURKEY POINT - UNITS 3
- 5. 4 3/4 3-13 AMENDMENT NOS.
AND
0H FUNCTIONAL UNIT TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS ALLOWABLE, VALUE 8 TRIP SETPOINT U3l 0
I.
Safety Injection (Reactor Trip, Turbine Trip, Feedwater Isolation, Control Room Ventilation Isolation, Start Diesel Generators, Containment Phase A Isolation (except Manual SI),
Containment Cooling Fans, Containment Filter Fans, Start Sequencer, Component Cooling Water, Start Auxiliary Feedwater and Intake Cooling Water) a.
Manual Initiation b.
Automatic Actuation Logic c.
Containment Pressure--High d.
Pressurizer Pressure--Low e.
High Differential Pressure Between the Steam Line Header and any Steam Line.
f.
Steam Line Flow--High N.A.
N.A.
<4a5 psig
>1712 psig
<114 psig
<A function defined as follows: A hP corres-ponding to 42.6%
steam flow at O%%u load increasing linearly from 2N load to a value corresponding to 122.61 steam flow at full load.
N.A.
N.A.
<4.0 psig
>1730 psig
<100 psi
<A function defined as ~
follows: A bP corres-ponding to 4R steam flow at 0/ load in-creasing linearly from 2Nd load to a value corresponding to 120 X steam flow at full load.
0H I
FUNCTIONAL UNIT Coincident with:
Steam Generator Pressure--Low or T~--Low TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUHENTATION TRIP SETPOINTS ALLOWABLE
~ALUE I
>588 psig
>542.5'F RIP SETPOINT
>614 psig
>543'F U
0 2.
Automatic Actuation Logic and Actuation Relays b.
Containment Pressure--High-High Coincident with:
Containment Pressure--High 3.
Containment Isolation a.
Phase "A" Isolation 1)
Manual Initiation 2)
Automatic Actuation Logic and Actuation Relays 3)
Safety Injection b.
Phase "B" Isolation 1)
Hanual Initiation N.A.
<22.6 psig
<4.5 psig N.A.
N.A.
See Item 1 above for all Safety Injection Allowable Values.
N.A.
N.A.
<20.0 psig
<4.0 psig N.A.
N.A.
See Item 1 above for all Safety Injection Trip Setpoints.
N.A.
0M UNCTIONAL UNIT TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUHENTATION TRIP SETPOINTS ALLOWABLE
~VLUE 8 TR P SETPOINT Ug 0
3.
Containment Isolation (Continued) 2)
Automatic Actuation Logic and Actuation Relays 3)
Containment Pressure--
High-High Coincident with:
Containment Pressure--High c.
Containment Ventilation Isolation 1)
Containment Isolation Manual Phase A or Manual Phase B
2)
Automatic Actuation Logic and Actuation Relays 3)
Safety Injection 4)
Containment Radio-activity--High (1) 4.
Steam Line Isolation a.
Manual Initiation N.A.
<22.6 psig
<4.5 psig N.A.
N.A.
See Item 1.
above for all Safety Injection Allowable Values.
Particulate (R-11)
<6.8 x 10 CPM Gaseous (R-12)
See Note 2
N.A.
N.A.
<20.0 psig
<4.0 psig N.A.
N.A.
See Item l. above for all Safety Injection Trip I Setpoints.
Particulate (R-ll)
<6.1 x 10~
CPM Gaseous (R-12)
See Note 2
N.A.
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 0H EIINCTIONAL IINIT 4.
Steam Line Isolation (Continued) b.
Automatic Actuation Logic and Actuation Relays c.
Containment Pressure--High-High Coincident with:
Containment Pressure--High d.
Steam Line Flow--High ALLOWABLE VALUE 8 N.A.
<22.6 psig
<4.5 psig
<A function defined as-follows: A dP cor res-ponding to 42.6%%u steam flow at O%%u load increasing linearly from 20%%u load to a value corresponding to 122.6%%u steam flow at full load.
TRIP SETPOINT N.A.
<20.0 psig
<4.0 psig
<A function defined follows: A & corres-ponding to 40%%u steam flow at O%%u load in-creasing linearly from 20%%u load to a value corresponding to 120%%u.
steam flow at full load.
az 0
Coincident with:
Steam Line Pressure--Low or T
--Low 5.
Feedwater Isolation a.
Automatic Actuation Logic and Actuation Relays b.
Safety Injection
>588 psig
>542.5'F N.A.
See Item l. above for all Safety Injection Allowable Values.
>614 psig
>543'F N.A.
See Item l. above for all Safety Injection Trip Setpoints.
FUNCTIONAL UNIT TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS ALLOWABLE VALUE V TRIP SETPOINT 5.
Feedwater Isolation (Continued) c.
Steam Generator Water Level High-High
<81.9X of narrow range instrument span
<8Ã of narrow range instrument span 6.
Auxiliary Feedwater (3) a.
Automatic Actuation Logic and Actuation Relays b.
Steam Generator Water Level--Low-Low c.
Safety Injection d.
Bus Stripping e.
Trip of All Main Feedwater Pump Breakers N.A.
<13% of narrow range instrument span.
See Item 1.
above for all Safety Injection Allowable Values.
See Item 7. below for all Bus Stripping Allowable Values.
N.A.
N.A.
>15% of narrow range instrument span.
See Item 1.
above for all Safety Injection Trip Setpoints.
See Item 7. below for all Bus Stripping Trip Setpoints.
N.A.
7.
Loss of Power a.
- 4. 16 kV Busses A and B
(Loss of Voltage)
N.A; N.A.
FUNCTIONAL UNIT 7.
Loss of Power (Continued) b.
480V Load Centers Degraded Voltage Load Center 3A 3B 3C 3D 4A 4B 4C TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM
'NSTRUMENTATION TRIP SETPOINTS ALLOWABLE VALUE V
[1
[]
[]
[]
[]
[]
[]
[]
TRIP SETPOIN 434V i5V (10 sec tl 430V t5V (10 sec 11 sec delay) sec delay) ~
430V 15V (10 sec il sec delay) 438V 25V (10 sec il sec delay) 434V-25V (10 sec il sec delay) 434V 15V (10 sec il sec delay) 435V iSV (10 sec il sec delay) 434V i5V (10 sec il sec delay)
Coincident with:
Safety Injection and See Item 1. above for all See Item 1.
above for all Safety Safety Injection Injection Trip Setpoints.
Allowable Values.
Diesel Generator Breaker Open N.A.
N.A.
FUNCTIONAL UNIT 7.
Loss of Power (Continued) c.
480V Load Centers Degraded Voltage Load Center 3A 3B 3C 3D 4A 4D Coincident with:
Diesel Generator Breaker Open TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TR P SETPOINTS ALLOWABLE VALUE f
[l
[1
[)
[1
[)
[)
[f
[)
N.A.
TR S TPOINT 434V i5V (60 sec i30 434V i5V (60 sec 130 sec delay) sec delay) ~
N.A.
424V i5V (60 sec f30 sec delay)
¹27V i5V (60 sec 130 sec delay) 437V 15V (60 sec 130 sec delay) 435V.iSV (60 sec 130 sec delay) 430V i5V (60 sec l:30 sec delay) 436V i5V (60 sec i30 sec delay)
0HX FUNCTIONAL UNIT 8.
Engineering Safety Features Actuation System Interlocks a.
Pressurizer Pressure b.
Tavg--Low TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS ALLONBLE VALUE 0
<2018 psig
>542.5'F TRIP SETPOINT Nominal 2000 psig Nominal 543'F O
U 0M 9.
Control Room Ventilation Isolation a.
Automatic Actuation Logic and Actuation Relays b.
Safety Injection c.
Containment Radioactivity--
High (1) d.
Containment Isolation Manual Phase A or Manual Phase B
e.
Air Intake Radiation Level N.A.
See Item 1.
above for all Safety Injection Allowable Values.
Particulate (R-11)
<6.8 x 10~
CPM Gaseous (R-12)
See Note 2
N.A.
<2.83 mR/hr N.A.
See Item 1.
above for all Safety Injection Trip Setpoints.
Particulate (R-11)
<6.1 x 10'PM Gaseous (R-12)
See Note 2
N.A.
<2 mR/hr
0H I
TABLE 3.3-3 (continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TABLE NOTATIONS (1)
Either the particulate or gaseous channel in the OPERABLE status will satisfy this LCO.
ltl I ti tt I it ttttt
~3I It'tt,
(
F
)
C t i t I II it 511 51 II I
~3.5 15'tt,
(
F
)
Where F
Actual Pur e Flow Design Purge Flow (35,000 CFH)
Setpoint may vary according to current plant conditions provided that the release rate does not exceed allowable limits provided in Specification 3. 11.2.1.
(3)
Auxiliary feedwater manual initiation is included in Specification 3.7.1.2.
!".'Cl Li,:
l::,,CfgtgÃeei 15!5'!.5-,.i I AA.:,.:,-.5 tt:~,, '::.,'5 I
-;:-tl 'It.::::::::i:: ',-ll I tt 55'Sf%'I~
C:
ao
)
-3 4.3 INSTRUMENTATION BASES ei
~
3 4.3.1 and 3 4.3.2 REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensures that:
(1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance (due to plant specific design, pulling fuses and using jumpers may be used to place channels in trip), and (4) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.
The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.
The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
Under some pressure and temperature conditions, certain surveillances for Safety Injection cannot be performed because of the system design.
Allowance to change modes is provided under these conditions as long as the surveillances are completed within specified time requirements.
The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-3 are the nominal values at which the bistables are set for each functional unit.
The setpoint is considered to be adjusted consistent with the nominal value when the "as measured" setpoint is within the band allowed for calibration accuracy.
d'i midiiice"'i'0i><'6 'i:"iif~U'"%itb'184th'i~%%1iiii'il~Tjiiiilfi'iid<'"1ii'diis~fg~i'i"doe&mii'if'5iYYn"it TURKEY POINT - UNITS 3
& 4 B 3/4 3-1 AMENDMENT NOS.
AND
r INSTRUMENTATION BASES rRACQR P
S S
MA D G
~INNT TT N(C I
d)
D SA E
S S
The methodology to derive the Trip Setpoints includes an allowance for instrument uncertainties.
Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties.
Sensor and rack instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes.
I!~h i,:,':iidi':::ll 'iiiiii'"iTCI Q!
IT( T!TTTTITT Tll!ITTN 'ITIIIIi!TllIIhl ITT'I 'lh I:!I'Ihdi"J'I!II/!idll:"
""jifgbii'at'il'6l'i'jar'i::;>>!d7iikiijf!xiii'iidiiiied:,.c'a1"1b'i%tiki rir&'hIv'it'3'i'i~
The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combina-tions indicative of various accidents
- events, and transients.
Once the required logic combination is completed, the system sends actuation signals to TURKEY POINT UNITS 3 5 4 B 3/4 3-la AMENDMENT NOS.
AND
e
'%a(
4 ~