ML19351A359

Proposed Tech Spec Re Reduction of Nonconservatism Allowed in Power Level Measurements & Frequency of Adjusting Measured Power to Match Calculated Secondary Power

ML19351A359
Person / Time
Site:	Waterford
Issue date:	10/16/1989
From:	LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML19351A358	List: ML19351A357 ML19351A359
References
NUDOCS 8910200114
Download: ML19351A359 (5)

Text

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TABLE 4.3-1 (Continued)

J 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.

1. The ptovisions of Specificatigg 4.0.4 are not applicable when reducing reactor power to less than }9 '% of RATED THERMAL POWER from a reactor ter than 10 '% of RATED THERMAL POWER. Upon reducing power power below level10grgg% of RATED THERMAL POWER, a CHANNEL FUNCTIO 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.

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

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

(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 difference is greater than 2%. During 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 OPERA 8ILITY including alarm and/or trip functions.

(7) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rata as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant 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 in:1uded 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 verificatien 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.

WATERFORD - UNIT 3 3/4 3-12 AMENDMENT NO.40

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/ .- TABLE 4.3-1 (Continu:d)

. 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. The reactor ptovisions power toofless Specificatigg%

than }9 of RATED THERMAL POWER from a react ter than 10 % of RATED THERMAL POWER. Upon reducing power power below level10grfg% of RATED THERMAL POWER, a CHANNEL FUNCTION 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.  !

(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. -

(2) a_boveJ5%

Heat balance only (CHANNEj,JLNCTIONAL TESI_ not induded),ials oLRATEDTHERMALPOWERjadjustthe~LinearPodr7evelsTei and the ReMcc CPC ada~risisabTe cons _ tant nultipliers to make the CPC AT power and CPC wit s nuclear power calculations agree with the calorimetric _ calculation il -

[f;*] absplutAdifference is greater th JanM urin ~g THYSICS TESTS, these wac Psw dilly cali5 tatters iiray'be suspefMed provided these calibrations are t performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

l -(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 OPERA 8ILITY including 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 pump differential i pressure instrumentation or by calorimetric calculations and if necessary, I adjust the CPC addressable constant flow coefficients such that each l 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 i 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.

l (9) The monthly CHANNEL FUNCTIONAL TEST shall include verification that i the correct values of addressable constants are installed in each l OPERABLE CPC.

(10) At least once per 18 months and following maintenance or edjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage trip function and the shunt trip function.

WATERFORD - UNIT 3 3/4 3-12 AMENDMENT NO.40 1

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Compare.the'PPS Linear Power, the CPC Delta-T Power and'the'CPC Nuclear-

, l 1 Power' signals'to'the calorimetric calculation.- If'a signal-is less than -l the calorimetric calculation by more than 1% of RATED THERMAL POWER,~ adjust- .i

+ it.to be' greater then or equal to the. calorimetric calculation. >

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