ML17311A502

Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators

ML17311A502
Person / Time
Site:	Palo Verde
Issue date:	12/07/1994
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17311A500	List: ML17311A502
References
NUDOCS 9412220179
Download: ML17311A502 (3)

Text

FOR INFORMATION ONLY TABLE 4.3-1 (Continued)

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

Each STARTUP or when required w>th the reactor trip breakers closse d and the CEA drive s ystem capable of rod withdrawal if not performed in the previous 7 days.

(2) Heat balance only (CHANNEL FUNCTIONAL TEST not included) above 15K s f RATE L POWER; adjust the linear power level, the CPC delta T power and CPC nuclear power signals to agree with i thee ca 1 orimetric so u e ifference is greater than 2X. During PHYSICS these daily calibrations may be suspended provided ovi e th ese cal ibrati ons ar e performed er for upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

(3) Above 15K of RATED THERMAL POWER veri verify th att th the 1' linear power sub-channel ne gains o the excore detectors are consiste n t wi th th e values ains of ablish the shape annealing matrix elementss in thee Cor used to establish ore Protection Calculators.

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

(5) After each fuel loading and prior to exceeding 70K of RATE THERMAL uel loa POWER annealing matrix elements ~

the i ncor e detectors shall be used to determine he shape used in the Core Protection Calculators-eh~

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.

Above 70K of RATED THERMAL POWER, verify that the total steady-state RCS flow r ate 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 cons coef,:cients such that each CPC indicated flow is less than or ant'low equal to the actual flow rate. The flow measurement uncertainty may be included in the BERR1 term in the CPC and is equal too or greater t than 4X.

Above 70% of RATED THERMAL POWER, verify that the total steady-state 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 pressure instrumentation and the ultrasonic flow meter adjusted pump curves or calorimetric calculations.

The monthly CHANNEI FUNCTIONAL TEST shall include verification that the correct current 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 ver ificati n of the undervoltage and shunt trips.

9412220179 941207 j PDR ADOCK 05000528 P PDR PALO VERDE " UNIT 1 3l4 3-1ts

t FOR INFORMATION ONI Y t

TABLE 4. 3-1 Continued)

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS TABLE NOTATIONS With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

Each STARTUP or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, in the previous 7 days, if not performed (2) Heat balance only (CHANNEL FUNCTIONAL TEST not included), above 15K of RATED THERMAL POWER; adjust the linear power level, the CPC delta T power and CPC nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than ZX. 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 o the next major test power plateau.

(3) Above 15K 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 70K of RATE THERMAL annealing matrix elements ~

POWER, the incore detectors shall be used to determine the shape Used the Core Protection Calculators ~H+

ln (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.

(7) Above 70K of RATED THERMAL POWER, verify that the total steady-state 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 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 may be included in the BERRl term in the CPC and is equal to or greater than 4X.

(8) Above 7'f RATED THERMAL POWER, verify that the total steady-state 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 pressure instrumentation and the ultrasonic flow meter adjusted pump curves or calorimetric calculations.

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

(1O) 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 and shunt trips.

- AMEi"JD.".~NT 'lO. 3o PALO VERDE UNIT 2 3/4 3-16

0 ~

FOR INFORMATION ONLY TABLE 4.3-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS TABLE NOTATIONS With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

(i)- 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) Heat balance only (CHANNEL FUNCTIONAL TEST not included}, above 15K of RATED THERMAL POWER; adjust the linear power level, the CPC delta T power and CPC nuclear power signals to agree with the calorimetric calculation if absolute difference is greater than 2X. 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 15K 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.

0l't'.I'Ifv (4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) After each fuel loading and prior to exceeding 70K of RATED THERMAL annealing matrix elements ~

POWER, the incore detectors shall be used to determine the shape USCd the Core Protection Calculators ~A+

Ill 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 andlor trip functions.

(7) Above 70K of RATED THERMAL POWER, verify that the total steady-state 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 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 may be included in the BERRl term in the CPC and is equal to or greater than 4X.

Above 70K of RATED THERMAL POWER, verify that the total steady-state 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 pressure instrumentation and the ultrasonic flow meter adjusted pump curves or calorimetric calculations.

(9)- The monthly CHANNEL FUNCTIONAL TEST shall include verification that the correct (current) 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 and shunt trips.

- UNIT 3/4 3"16 AMENDMENT NO. 27 PALO VERDE 3