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Tech Spec Change Request 98 Re Power Levels for Reactor Coolant Pumps
	ML20053D275
Person / Time
Site:	Crystal River
Issue date:	05/28/1982
From:	; FLORIDA POWER CORP.
To:	;
Shared Package
ML20053D266	List: ML20053D265; ML20053D275; ML20053D278;
References
	TAC-48471, TAC-48844, NUDOCS 8206040254
	Download: ML20053D275 (8)
	v • d • e

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2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS The Reactor Protection System Instrumentation Trip Setpoint specified in Table 2.2-1 are the values at which the Reactor Trips are set for each parameter. The Trip Setpoints have been selected to ensure that the reactor core and reactor coolant system are prevented from exceeding their safety limits. Operation with a trip setpoint less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

The Shutdown Bypass provides for bypassing certain functions of the Reactor Protection System in order to permit control rod drive tests, zero power PHYSICS TESTS and certain startup and shutdown procedures.

The purpose of the Shutdown Bypass RCS Pressure-High trip is to prevent normal operation with Shutdown 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 Nuclear Overpower Trip Setpoint of < 5.0% prevents any significant reactor power from being produced. Sufficient natural circulation would be available to remove 5.0% of RATED THERMAL POWER if none of the reactor coolant pumps were operating.

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

Nuclear Overpower A Nuclear Overpower trip at high power level (neutron flux) provides reactor core protection against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry.

During Cycle IV, the Nuclear Overpower trip at high power level also assures operation at power levels for which the three pump coastdown analyses are valid.

During normal station operation, reactor trip is initiated when the reactor power level reaches 102.03% of rated power. Due to calibration an l instrument errors, the maximum actual power at which a trip would be actuated could be 109.15%, which was used in the safety analysis. l CRYSTAL RIVER - UNIT 3 8 2-4 Amendment No.

8206040254 820528 PDR ADOCK 050003C2 p PDR

-- 12 0

(-17,101.3) ^ - -

^ (10,101.3) 10 0 ACCEPTABLE 4 PUMP

(-33,91) ( OPERATION . . )gg

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(-17,75.67) ^ ^ 10,75.67)

(-33,6s37) < 3g g

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n ACCEPTABLE NUCLEAR 3 8 4 PUMP - - OVERPOWER OPERATION

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-60 -50 -40 -30 -20 -IO O 10 20 30 40 50 60

' REACTOR POWER IMBALANCE */o l

'. FIGURE 2.2-1 TRIP SETPOINT FOR NUCLEAR OVERPOWER BASED ON RCS FLOW AND AXIAL POWER IMBALANCE l

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CRYSTAL RIVER - UNIT 3 2-7 ,

TABLE 2.2-1 x

REACTOR PROTECTION SYSTEM INSTRUMENTATION TRIP SETPOINTS .

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BE FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES -

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1. Manual Reactor Trip Not Applicable Not Applicable EE 2. Nuclear Overpower < 102.0% of RATED THERMAL POWER < 102.0% of RATED THERMAL POWER

-4 with four pumps operating with four pumps operating w

< 59.70% of RATED THERMAL POWER < 59.70% of RATED THERMAL POWER with three pumps operating with three pumps operating

3. RCS Outlet Temperature-High < 618 F < 618 F

4. Nuclear Overpower Trip Setpoint not to Allowable Values not to exceed no Based on RCS Flow and exceed the limit line of the limit line of Figure 2.2-1 5, AXIAL POWER IMBALANCE (1) Figure 2.2-1

5. RCS Pressure-Low (1) }; 1800 psig 2; 1800 psig

6. RCS Pressure-High > 2300 psig < 2300 psig

7. RCS Pressure-Variable Low (I) > (11.59 Tout F - 503). ) }; (11.59 Tout F - 5037.8) psig

, psig.

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AUCEP7ABLE 4 PUMP

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REACTOR POWER IMBALAAW.*/o >

FIGURE 2.1 , .

REACTOR CORE SAFETY LIMIT CRYSTAL RIVER - UNIT 3 2-3 v ~- -

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LIMITING SAFETY SYSTEM SETTINGS BASES The AXIAL POWER IMBALANCE boundaries are established in order to prevent reactor thermal limits from being exceeded. These thermal limits are

either power peaking kw/f t limits or DNBR limits. The AXIAL POWER IM-BALANCE reduces the power level trip produced by the flux-to-flow ratio such that the boundaries of Figure 2.2-1 are produced. The flux-to-flow ratio reduces the power level trip and associated reactor power-reactor power-imbalance boundaries by 1.013% for a 1% flow reduction. l RCS Pressure - Low, High, and Variable Low The High and Low trips are provided to limit the pressure range in which reactor operation is permitted.

During a slow reactivity insertion startup accident from low power or a slow reactivity insertion from high power, the RCS Pressure-High set-point is reached before the Nuclear Overpower Trip Setpoint. The trip setpoint for RCS Pressure-High, 2300 psig, has been established to main-tain the system pressure be?ow the safety limit, 2750 psig, for any de-sign transient. The RCS Pressure-High trip is backed up by the pressur-izer code safety valves for RCS over pressure protection and is, there-fore, set lower than the set pressure for these valves, 2500 psig. The RCS Pressure-High trip also backs up the Nuclear Overpower trip.

The RCS Pressure-Low,1800 psig, and RCS Presse re-Variable Low, (11.59 Tout F-5037.8) psig, Trip Setpoints - e been established to maintain the DNB ratio greater than or equai to 1.30 for those design accidents that result in a pressure reduction. It also prevents reactor operation at pressures below the valid range of DNB correlation limits, protecting against DNB.

Due to the calibration and instrumentation errors, the safety analysis used a RCS Pressure-Variable Low Trip Setpoint of (11.59 Tout

F-5077.8)psig.

CRYSTAL RIVER - UNIT 3 B 2-6 Amendment No.

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LIMITING SAFETY SYSTEM SETTINGS BASES RCS Outlet Temperature - High <

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, j, 1 The RCS Outlet Temperature High trip f 618 F prevents the ~ reactor' outlet' temperature from exceeding the design limits and acts as a backup trip z for all power excursion, transients. -'

i Nuclear Overpower Based 'n oRCS Flow and AXIAL POWER IMBALANCE The power level trip seipoint pr'/duced by the reactor coolant system flow is based on a flux-to-flocratio which.has been established to ac-commodate flow decreasing trans' tents. from high power.

The power level trip setpoint produced by the' power-to-flow ratio pro-vides both high power level and low flow protectfon in the event the re-actor power level increases or the reactor coolant flow rate decreases.

The power level setpoint produced by the powar-to-flow ratio provides overpower DNB protection for all modes of pump operation. For every flow rate there is a maximum permissible power level, and for every pow-er level there is a minimum permissible low flow rate. Typical power level and low flow rate combinations for the pump sMuations of Table 2.2.1 are as follows:

5

1. Trip would occur when four reactor csolant pumps are operating if power is > 101.3% and reactor flow rate As 100%, or flow rate is f 96703% and power level is 97.28%. q ,

2. Trip would occur when three reactor coolant iumps i^ are cNrat-ing if power is > 75.67% and reactor flow rate is 74.7%, or flow rate is f ST.29% and power is 55%.

For safety calculations the maximun calibration and instrumentation er- i' rors for the power level were used. ,

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CRYSTAL RIVER - 1 NIT 3 B 2-5 Amemdment No.

TABLE 3.3-1 (Continued)

T_ABLE NOTATION

With the control rod drive trip breakers in the closed position and the control rod drive system capable of rod withdrawal.

- When Shutdown Bypass is actuated.

- - For one time only, the reactor coolant pump power monitor trip function may be manually bypassed in Modes 1 and 2 (at less than 40% Full Power) for the duration of special testing. These tests are to be conducted following startup from the unit outage which began on January 28, 1982.

4

The provisions of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above 10-10 amps on both Intermediate Range channels.

(a) Trip may be manually bypassed when RCS pressure 11720 psig by actuating Shutdown Bypass provided that:

(1) The Nuclear Overpower Trip Setpoint is f 5% of RATED THERMAL POWER, I (2) The Shutdown Bypass RCS Pressure--High Trip Setpoint of f 1720 psig is imposed, and (3) The Shutdown Bypass is removed when RCS pressure > 1800 psig.

(b) Trip may be manually bypassed when reactor power is less than or equal to 2475 MWt.

ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or l open the control rod drive trip breakers.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels STARTUP and/or POWER OPERATION may proceed provided all of the following conditions are l

satisfied:

a. The inoperable chanael is placed in the tripped condition within one hour.

b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1,

! CRYSTAL RIVER - UNIT 3 3/4 3-3 i

I .

REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.4.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.

APPLICABILITY: As noted below, but excluding MODE 6.*

ACTION:

MODES 1 and 2:

a. With one reactor coolant pump not in operation, STARTUP and POWER

, OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 59.70% of RATED THERMAL POWER and within 4 l hours the setpoints for the following trips have been reduud to the values specified in Specification 2.2.1 for operation with three reactor coolant pumps operating:

1. Nuclear Overpower MODES 3, 4 and 5:

a. Operation may proceed provide <i at least one reactor coolant loop is in operation with an associated reactor coolant pump or decay heat removal pump.

1 i b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.4.1 The Reactor Protective Instrumentation channels specified in the l applicable ACTION statement above shall be verified to have had their trip l

setpoints changed to the values specified in Specification 2.2.1 for the applicable number of reactor coolant pumps operating either:

I a. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after switching to a different pump combination if l the switch is made while operating, or

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

See Special Test Exception 3.10.3.

CRYSTAL RIVER - UNIT 3 3/4 4-1 Amendment No.

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BAW-1684, Rev. 2 May 1982 l

18 I

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CRYSTAL RIVER UNIT 3

- Cycle 4 Reload Report -

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I Babcock &Wilcox g . .. ............

ML20053D275

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