ML20069Q038

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Proposed Tech Specs,Adjusting 3 Plant Protection Sys Trip Setpoints & Allowable Values
ML20069Q038
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/22/1994
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20069Q025 List:
References
NUDOCS 9406270215
Download: ML20069Q038 (7)
v • d • e


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l l TABLE 2.2-1 REACTOR PROTECTIVE INSTRtNENTATION TRIP SETPolNT LIMITS E$8s FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

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ou h 1. Manual Reactor Trip Not Appilcable Not Applicable 9G 2. Linear Power Laval - High OA Four Reactor Coolant Pumps 1 110.1% of RATED THERNAL POWER $ 110.7% of RATED THERMAL POWER l @ Operating

3. Logarithele Power Level - High (1) 1 0.257% of RATED THERMAL POWER 1 0.275% of RATED THERNAL POWER
4. Pressurizer Fressure - High 1 2365 psia 1 2372 psia
5. Pressurizar Pressure - Low 1 1684 psia (2) > 1644 psia (2) m 6. Containment Pressure - High i 17.1 psia i 17.3 psia
7. Steam Generator Pressure - Low > 764 psia (3) > 748 psia (3)
8. S Ram Generator Level - Low > 27.4% (4) > 26.7% (4)
9. Local Power Density - High 1 21.0 kW/ft (5) i 21.0 kW/ft (5)
10. 05R - Low > 1.26 (5) > 1.26 (5)
11. Steam Generator Level - High i 87.7% (4) 1 88.4% (4)
12. Reactor Protection Systes Logic Not Applicable Not Applicable
13. Reactor Trip Breakers Not Applicable Not Applicable 5 14. Core Protection Calculators Not Arc ) cable Not Applicable

% 15. CEA Calculators Not .wplicable Not Appilcable 1 16. Reactor Coolant. Flow - Low > 23.8 psid (7) > 23.6 psid (7)

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g TABLE 3.3-4 (Continued) d EIEIIEERES SAFETY FEATURES ACTUATICII SYSTEM INSTRIBENTATION TRIP VALUES a

U ALLOWABLE

, FINICTIGIIAL lAIIT itIP VALUE VALUES

5. SAFETY lluECTIN SV5IM Sist BECIRCULATICII (RAS)

" a. Ilonnel BAS (Trip Buttans) Not Applicable feet Appilcable ,

b. BefuelleA3 h Sterage Peel - Lou 18. 5 (57,967 gallons) 9. R (53,910 gallons)
c. Autametic Actmetles Logic IIst Applicable Not Appilcable
6. LD55 SF PGES
a. 4.M kW Emergency Bus IInderveltage 1 3245 velts 1 3245 volts (Lees of Weltage)

, b. 400 V Emergency Bus Moderveltage 1 372 volts 1 354 volts D c. 4.16 kV Emergency tus underveltage y (tograded Westage) 1 3875 velts 1 3860 volts l 5 7. EMantacV FEEmmTES (EFAS)

a. Ilmamel (Trip Suttans) llet Applicable flot Applicable
b. Steam Generator (lat) Level - Lew I3) I4) > 26.7X I3I I4) 1 27.45
c. ' Steam Generator er - Nigh (SG-1 > SG-2) i 127.6 psid 1 IM.6 psid
d. Skeen Generater AP - Ni p (SG-2 > SG-1) $ 127.6 psid i IM.6 psid -
e. Steam Generator (1&2) Pressure - Lew 1 764 psla(2) 74g ,,g,(2) i f. Autaastic Actuation Logic Ilot Applicable flot Applicable a g. Centrol Valve Logic (Mies Range SG Level - Lou) 1 36.3E(3) (5) > 35.3%(3) (5) ,

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=

a

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS ._ _ _ _ _ _ l BASES i

Manual Reactor Trip The Manual Reactor Trip is a redundant channel to the automatic protective  ;

instrumentation channels and provides manual reactor trip capability.

Linear Power Level - High The Linear Power Level - High trip provides reactor core protection against rapid reactivity excursions which might occur as the result of an ejected CEA. This trip initiates a reactor trip at a linear power level of less than or equal to 110.1% of RATED THERMAL POWER.

Logarithmic Power Level - High The Logarithmic Power Level - High trip is provided to protect the integrity of fuel cladding and the Reactor Coolant System pressure boundary in the event of an unplanned criticality from a shutdown condition. A reactor trip is initiated by the Logarithmic Power Level - High trip at a THERMAL POWER level of less than or equal to 0.2575 of RATED THEMAL POWER unless this trip is manually bypassed by the operator. The operator may manually bypass this trip when the THERMAL POWER level is above 10 *5 of RATED THERMAL POWER; this bypass is automatically removed when the THElBEL POWER level decreases to 10 *% of RATED THERMAL POWER. i Pressurizer Pressure - High The Pressurizer Pressure - High trip, in conjunction with the pressurizer safety valves and main steam safety valves, provides Reactor Coolant Systes protection against overpressurization in the event of loss of load without' reactor trip. This trip's setpoint is at less than or equal to 2365 psia which is below the nominal lift setting 2500 psia of the pressurizer safety valvas and its operation avoids the undesirable operation of the pressurizer safety valves.

Pressurizer Pressure - Low The Pressurizer Pressure - Low trip is provided to trip the. reactor and to assist the Engineered safety Features System in the event of a Loss of Coolant Accident. During normal operation, this trip's setpoint is set at greater than or equal to 1884 psia. This trip's setpoint any be manually decreased, to a minism value of 100 psia, as pressurizer pressure is reduced during plant shutdowns, provided the margin between the pressurizer pressure and this trip's setpoint is maintained at less than or equal to 400 psi; this setpoint increases automatically as pressurizar pressure ircreases until the trip setpoint is reached.

WATERFORD'- UNIT 3 8 2-3

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NPF-38-152 Attachment B 1

1 j

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1 1

--+w< e rrv = r,-- ,- w ,

TABLE 2.2-1 REN.70R PROTECTIVE INSTPANENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

1. Manual Reactor Trip Not Applicable Not Applicable t
2. Linear Power Level - High Four Reactor Coolant Punps s 108% of RATED THERMAL POWER s 108.76% of RATED THERMAL POWER l Operating
3. 1ogarithmic Power Level - High (1) s 0.257% of RATED THERHAL POWER s 0.275% of RATED THEPTAL POWER
4. Pressurizer Pressure - High s 2350 psia s 2359 psia l
5. Pressurizer Pressure - Low 2 1684 psia (2) 21644 psia (2)
6. Containment Pressure - High s 17.1 psia s 17.3 psia
7. Steam Generator Pressure - Low 2 764 psia (3) 2 748 psia (3)
8. Steam Generator Level - Low 2 27.4% (4) 2 26.7% (4)
9. Local Power Density - High s 21.0 kW/ft (5) s 21.0 kW/ft (5)
10. DNBR Low 2 1.26(5) 2 1.26 (5)
11. Steam Generator Level - High s 87.7% (4) s 88.4% (4)
12. Reactor Protection System Logic Not Applicable Not Applicable
13. Reactor Trip Breakers Not Applicable Not Applicable
14. Core Protection Calculators Not Applicable Not Apolicable
15. CEA Calculators Not Applicable Not Applicable
16. Reactor Coolant Flow - Low 2 23.8 psid (7) 2 23.6 psid (7)

WATERFORD 'JNIT 3 2-3

TABLE 3.3-4 -

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ALLOWABLE FUNCTIONAL UN.IT TRIP VALUE VALUES

5. SAFETY INJECTION SYSTEM SUMP RECIRCULATION (RAS)
a. Manual RAS (Trip Buttons) Not Applicable Not Applicable
b. Refueling Water Storage Pool - Low 10.0% (57,967 gallons) 9.3%(53,910 gallons)
c. Automatic Actuation Logic Not Applicable Not Applicable
6. LOSS OF POWER a, 4.16 kV Emergency Bus Undervoltage 2 3245 volts 2 3245 volts '

(Loss of Voltage)

b. 480 V Emergency Bus Undervoltage 2 372 volts 2 354 volts j c. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage) 2 3875 volts 2 3860 volts
7. EMERGENCY FEEDWATER (EFAS)
a. Manual (Trip Buttons) Not Applicable Not Applicable
b. Steam Generator (l&2) Level - Low 2 27.4% (3) (4) 2 26.7% (3) (4)
c. Steam Generator AP - High (SG-1 > SG-2) s 123 psid s 134 psid
d. Steam Generator AP - High (SG-2 > SG-1) s 123 psid s 134 psid
e. Steam Generator (l&2) Pressure - Low 2 764 psia (2) 2 748 psia (2)
f. Automatic Actuation Logic Not Applicable Not Applicable 9 Control Valve Logic (Wide Range 2 36.3% (3) (5) 2 35.3% (3) (5)

SG Level - Low)

WATERFORD - UNIT 3 3/4 3-20 l

' SAFETY' LIMITS AND LIMITING SAFETY SYSTEM SETTINGS BASES ~

Manual Reactor Trio The Manual Reactor Trip is a redundant channel to the automatic protective instrumentation channels and provides manual reactor trip capability.

Linear Power level - Hiah The Linear Power Level - High trip provides reactor core protection against rapid reactivity excursions which might occur as the result of an ejected CEA, This trip initiates a reactor trip at a linear power level of less than or equal to Log % of RATED THERMAL POWER. l Locarithmic Power Level - Hiah The Logarithmic Power Level - High trip is provided to protect the integrity of fuel cladding and the Reactor Coolant System pressure boundary in .

the event of an unplanned criticality from a shutdown condition. A reactor trip is initiated by the Logarithmic Power Level - High trip at a THERMAL POWER level of less than or equal to 0.257% of RATED THERMAL POWER unless this trip is manually bypassed by the operator. The operator may manually bypass this trip when the THERMAL POWER level is above 10-4 % of RATED THERMAL POWER; this bypass is automatically removed when the THERMAL POWER level decreases to 10-4 % of RATED THERMAL POWER.

Pressurizer Pressure - Hiah The Pressurizer Pressure - High trip, in conjunction with the pressurizer safety valves and main steam safety valves, provides Reactor Coolant System protection against over pressurization in the event of loss of load without j reactor trip. This trip's setpoint is at less than or equal to 2350 psia which is below the nominal lift setting 91 2500 psia o M 9I the pressurizer safety valves and its operation avoids the undesirable operation of the pressurizer safety valves.

Pressurizer Pressure - Low The Pressurizer Pressure - Low trip is provided to trip the reactor and to assist the Engineered Safety Features System in the event of a Loss of Coolant Accident. During normal operation, this trip's setpoint is set at greater than or equal to 1684 psia. This trip's setpoint may be manually decreased, to a minimum value of 100 psia, as pressurizer pressure is reduced during plant shutdowns, provided the margin between the pressurizer pressure and this trip's setpoint is maintained at less than or equal to 400 psi; this setpoint increases automatically as pressurinr pressure increases until the trip setpoint is reached.

WATERFORD - UNIT 3 B 2-3 i

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