ML20053D973

Tech Specs,App A,Reflecting Changes Contained in Cycle 3 Reload Rept

ML20053D973
Person / Time
Site:	Davis Besse
Issue date:	06/01/1982
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20053D585	List: ML20053D584 ML20053D970 ML20053D973
References
TAC-48044, NUDOCS 8206070492
Download: ML20053D973 (6)

Text

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Do C:N 00 Table 2.2-1. Reactor Protection System Instrumentation Trip Setpoints m Functional unit Trip setpoint oru .

Allowable values OS 1. Manual reactor trip Not applicable.

Not applicable.

$SS 1c5.1 %

N 2. liigh flux 105.1 5!0';.0% of RATED THERMAL POWER with four pumps operating. 510&.-9% of RATED TilERMAL POWER with 6 four pumps operatingi 6

579.g% of RATED TilERMAL POWER with three pumps operating 179.)% of RATED THERMAL POWER Cith three pumps operatingF

3. RC high temperature 5618*F 5618'FI

4. Flux -- A flux / flow (1'4 Trip setpoint not to exceed the lim-it line of Figure 2.2-1 Allowable values not to exceed the limit line of Figure 2.2-1 I I cle 3.4 1963.4

5. RC low pressure (t) %WBF- psig 1993.4 21000.G psig* 21035.0 psig**

{[6. RC high pressure s2300 psig 2

s2300.0 psig* s2300.0 psig**

7. RC pressure ' temperature (1) s2 2(12.60 T, g *F - 46667 psig 2(12.60 T, g *F -> 4660) psigi

8. liigh flux / number of RC 1 pumps on(l) s'5'5.6l % of RATED THERMAL POWER withof RATED THERMAL POWER with s 55.8%

one pump operating in each loop one pump operating in each loop #

50.0% of RATED TilERMAL POWER with 50.0% of RATED THERMAL POWER with two pumps operating in one loop and two pumps operating in one loop and no pumps operating in the other loop no pump operating in the other loop I 50.0% of RATED TilERMAL POWER with no. 50.0%.of RATED THERMAL POWER with no pumps operating or only one pump op- pumps operating or only one pump op-erating eratingi

, 9. Containment pressure 54 psig 34 psigI high

FIGURE 8-3 TRIP SETPOINT FOR FLUX - A FLUX / FLOW

% RATED THERMAL POWER

- 120

-13.9 ,10 7.0 8 3,107.0 Mi s 1.15 2 4 PUMP M28 -1.619 CURVE SHOWS TRIP

- 10 0 SETPOINT FOR A 25%

i FLOW REDUCTION FOR f l THREE PUMP OPER ATION (290,100GPM ).THE ACTUAL l g

' TRIP SETPOINT'WILL BE i l DIRECTLY PROPCRTIONAL

- 33.0,85.0 TOTHE ACTUAL FLOW

-13.9,8 0.0 8.3,80.0 WITH THREE PUMPS.

i g 3 PUMP LI MIT l

.l LINES g g

33.0,67.0 1

-601 -

- 33.0 , 58 .0 ( l ., UNACCEPTABLE g

OPERATION ACCEPTABLE OPERATION FOR SPECIFIED RC PUMP COMBIN TION

) 33.0,4 0.0

-40l I

l UNACCEPTABLE l '

{ OPERATION I .

1 l

! - 20 o e a e

a sI la a a

e, 7l

=

I a <

m m lm m l ,

e i I l l 1 I I I>'

-60 -40 -20 0 20 40 60 AXIAL POWER IMBALANCE, %

e TECHNICAL SPECIFICATION FIGURE 2. 2-1 TRIP SETPOINT FOR FLUX 0, FLUX / FLOW 8-27 r

i 2.2. LIMITING SAFETT SYSTEM SETTINGS BASES 2.2.1. REACIOR PROTECTION SYSTEM INSTRIMENTATION SETPOINTS The reactor protection system instrumentation trip setpoint specified in Table 2.2-1 are the values jat which the reactor trips are set for each parameter.

The trip setpoints have been selected to ensure that the reactor core and re-actor coolant system are prevented from exceeding their safety limits.

The shutdown bypass provides for bypassing certain functions of the reactor protection system in order to permit control rod drive tests, zero power FHYSICS TESTS and certain startup and shutdown procedures. The purpose of the shutdown bypass high pressure trip is to prevent normal operation with shut-down bypass activated. This high pressure trip setpoint is lower than the normal low pressure trip setpoint so that the reactor must be tripped before the bypass is initiated. The high flux trip setpoint of 55.0% prevents any signifigant reactor power from being produced. Sufficient natural circulation would be available to remove 5.0% of RATED THERMAL POWER if none of the reac-tor coolant pumps were operating.

- ~ ~ - " - ~ ~ ~ ~ ~ ~~~

Manual Reactor Trip - - -

The manual reactor tr'ip is a redundant channel to the automatic reactor pro-tection system instrumentation channels and provides manual reactor trip capa-bility.

High Flux A high flux trip at high power level (neutron flux) provides reactor core pro-tection against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry.

-=-105if During normal station, operation, reactor trip is initiated when the reactor power level reaches-104.9% of rated power. Due to calibration and instrument errors, the maximum actual power at which a trip would be actuated could b::,

112%, which was used in the safety analysis.

DAVIS-BESSE, UNIT 1 B 2-4 8-7

... l 1

i LIMITING SAFETY SYSTEM SETTINGS l BASES I

RC High Temperature The RC high temperature trip 5618'F prevents the reactor outlet temperature from exceeding the design limits and acts as a backup crip for all power ex-cursion transients.

Flux - A Flux / Flow The power level trip setpoint produced by the. reactor coolant system flow is based on a flux-co-flow ratio which has been established to accommodate flow decreasing transients from high power where protection is not provided by the high flux / number of reactor coolant pumps on trips.

The power level trip setpoint produced by the power-to-flow ratio provides both high power level and low flow protection in the event the reactor power level increases or the reactor coolant flow rate decreases. The power level setpoint produced by the power-to-flow ratio provides overpower DNB protection for all modes of pump operation. For every flow rate there is a maximum per-missible power _ level, and for every_ power _ level _there 'is a =4ai m>= permissible low flow race. Examples of typical power level and low flow rate combinations for the pump situations of Table 2.2-1 that would result in a trip are as follows:

, 1.

m Io1+

Trip would occur when four reactor coolant pumps are operating if power is 125.1% and reactor coolant ficw rate is 100% of full flow rate, or flow of full flow rate and power level is 100%.

2.

rate is93SJr9%~t s

Trip would cccur when three reactor coolant pumps are operating if power is HM and reactor coolant flow race is 74.7% of full flow rate, or flow rate is MAI of full flow race and power is 75%.

$0f %7o-of.

For safety calculations the maximum calibration and instrumentation errors for the power level were used. Full flow rate in the above two examples is i defined as the flow calculated by the heat balance at 100% power.

I l

DAVIS-BESSE, UNIT 1 B 2-5 8-8 r

I

, l 3/4.4 REACTOR COOLANT SYSTEM -

3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION.

3.4.1.1 Both reactor coolant loops and both reactor. coolant pumps in each loop shall be in operation.

APPLICABILITY: MODES 1 and 2*. ,

ACTION: f cl, g

a. With one reactor coolant pump not in o eration, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than  % of RATED THERMAL l POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with three reactor coolant pumps operating: .

1. High Flux

2. Fl ux-AFl ux-Fl ow SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.2 The Reactor Protective Instrumentation channels specified in the applicable ACTION statement above shall be verified to have had their trip setpoints ch~anged to the values specified in Specification 2.2.1 for the applicable number of reactor. coolant pumps operating either:

~

a. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after swi[ching to a different pump combination if the switch is made while operating, or

b. Prior to reactor criticality if the switch is made whi.le shutdown.

• See Special Test Exception 3.10.3.

DAVIS-BESSE, UNIT 1 3/4 4-1 Amendment No. JC JY,' 38 C

Fi gure 8-1. REACTOR CORE SAFETY LIMIT 2600 - ,

2400 - .

RC HIGH PRESSURE TRIP 618.2300 O RC HIGH TEMPERATURE

c S 2200 -

WP h ACCEPTABLE 616,2127

__.._0PERATION _..___ .

RC PRESSURE-TEMPERATURE TRIP en4 ._ __./

60 6. 7, +985 SAFETY LIMIT 2000 -

RC LOW PRESSURE TRIP 1800 l

I I I I I 1 590 600 610 620 630 640 Reactor Outlet Temperature, *F TECHNICAL SPECIFICATION FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT 3-25

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