ML20154P949

Proposed Tech Specs Changing Original Tech Specs Table 4.3-1 to Add New Surveillance Requirement

ML20154P949
Person / Time
Site:	Waterford
Issue date:	05/20/1988
From:	LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20154P663	List: ML20154P949 W3P88-0993, Forwards Revised Tech Specs for Testing of Log Power Trip Based on Discussions W/Nrc.Changes Being Made to 880128 Submittal to Add New Surveillance Requirement.Safety Analysis Remains Bounding
References
NUDOCS 8806060136
Download: ML20154P949 (4)

Text

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TABLE 4.3-1 (Continued)

TABLE NOTATIONS "With the reactor trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

(1)

Each startup or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if not performed in the previous 7 days.

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(2)

Heat balance only (CHANNEL FUNCTIONAL TEST not included), above 1 of RATED THERMAL POWER: adjust the Linear Power Level signals and the CPC addressable constant multipliers to make the CPC AT power and CPC nuclear power calculations agree with the calorimetric calculation if absolute difference is greater than 2%.

During PHYSICS TESTS, these daily chlibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

(3)

Above 15% of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

After each fuel loading and prior to exceeding 70% of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall use these elements.

(6)

This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the channel as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions.

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(7)

Above 70% of RATED THERMAL POWER, verify that the total RCS flow M

rate as indicated by each CPC is less than or equal to the actual

'h RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric d

calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is less than equal to the actual flow rate.

included in the BERR1 term in the CPC and is equal to or great than 4%.

(8)

Above 70% of RATED THERMAL POWER, verify that the total RC3 flow rate as indicated by each CPC is less than or equal to the actual RCS,tatal' flow rate determined by calorimetric calculations.

(9)

The monthly CHANNEL FUNCTIONAL TEST shall include verification that the correct values of addressable constants are installed in each OPERA 8LE CPC, (10) At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage trip function and the shunt trip function, l.

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WATERFORD - UNIT 3 3/4 3-12 AMENDMENT NO. 5 88G6060136 8G0520 DR ADOCK 0500 2

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ATTAC11 MENT B i

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j TABLE 4.3-1 (Continued)

_ TABLE NOTATIONS

• With the reactor trip breakers in the closed position, the CEA drive l

system capable of.CEA withdrawal, and fuel in the reactor vessel.

6 (1) Each startup or when required with the reactor trip breakers closed Q

and the CEA drive system capable of rod withdrawal, if not performed in the previous 7 days.

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(2) Heat balance only (CHANNEL FUNCTIONAL TEST not included), above 15%

of RATED THERMAL POWER: adjust the Linear Power Level signals and the CPC addressable constant multipliers to make the CPC AT power and CPC nuclear power calculations agree with the calorimetric calculation if absolute aifference is greater than 2%.

During

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PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

(3) Above 15% of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) After each fuel loading and prior to exceeding 70% of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall use these elements.

(6) This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the channel as close to the sensors as practicable to verify OPERABILITY inclading alarm and/or trip functions.

(7) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant i

i pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is less than or equal to the actual flow rate.

The flow measurement uncertainty is included in the BERR1 term in the CPC and is equal to or greater than 4%.

(8) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by calorimetric calculations.

(9) The monthly CHANNEL FUNCTIONAL TEST shall include verification that the correct values of addressable constants are installed in each OPERABLE CPC, (10) At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage trip function and the shunt trip function.

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WATERFORD - UNIT 3 3/4 3-12 AMENOMENT NO. 5 i

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1. ' The provisions of Specification 4.0.4 are not applicable when reducing reactor power to less than 10-4. of RATED THERMAL POWER from a reactor 7

power level-greater than 10-4. of RATED THERMAL POWER. Upon reducing-7 power.below 10-4% of RATED THERMAL POWER, a CHANNEL FUNCTIONAL TEST shall.

be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if not performed during the previous 31' days.

This requirement does not apply with the reactor trip breakers open.

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