ML20212M614

Proposed Tech Specs 3/4.2.2 & 3/4.3.6,changing APRM Setpoints & Control Rod Block Instrumentation Setpoints, Respectively

ML20212M614
Person / Time
Site:	Fermi
Issue date:	03/09/1987
From:	DETROIT EDISON CO.
To:
Shared Package
ML20212M603	List: ML20212M602 ML20212M614
References
NUDOCS 8703120098
Download: ML20212M614 (2)

Text

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P POWER DISTRIBUTION LIMITS 3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The APRM flow biased neutron flux-high scram trip setpoint (S) and flow biased neutron flux-high control rod block trip setpoint (SRB) shall be established according to the following relationships: ,

TRIP SETPOINT ALLOWABLE VALUE S < (0.66W + 51%)T S < (0.66W + 54%)T S Sgg 5 (0.66W + 45%)T RB $ (0.66W + 42%)T where: S and S are in percent of RATED THERMAL POWER, RB W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 100 million 1bs/hr, at 100% of RATED THERMAL POWER T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER T is divided by the MAXIMUM FRACTION OF LIMITING POWER DENSITY.

applied only if less than or equal to 1.0 APPLICABILITY: OPERATIONAL CONLITIcH 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

ACTION:

With the APRM flow biased neutron flux-high scram trip setpoint and/or the

' flow biased neutron flux-high control rod block trip setpoint less conservative than the value shown in the Allowable Value column for S or SRB, as above determined, initiate corrective action within 15 minutes and adjust S and/or S gg tobecc.nsistentwiththeTripSetpointvalue*withinghoursorreduce' l THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.2 The FRTP and the MFLPD for each class of fuel shall be determined, the value of T calculated, and the most recent actual APRM flow biased neutron

' flux-high scram and flow biased neutron flux-high control rod block trip setpoints verified to be within the above limits or adjusted, or the APRM gain readings shall be verified as indicated below,* as required:

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and

c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with MFLPD greater than or equal to FRTP.

d. The provisions of Specification 4.0.4 are not applicable.

"With MFLPD greater than the FRTP during pawer ascension up to S0% of RATED THERMAL POWER, rather than adjusting the APRM setpoints, the APRM gain may be adjusted such that APRM readings are greater than or equal to 100% times MFLPD, provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER and a notice of adjustment is posted on the reactor control panel.

FERMI - UNIT 2 3/4 2-5 8703120098 670309 PDh ADOCKOSOOg1 P - - - _ _ _ _ - _ _ - _ _ - - _ _ -

e

.E 3.3.6-2 .

CONTROL ROD BLOCK INSTRUM[NTATION SETPOINTS ..

TRIP SETPolNT ALLOWASLE VALUE .

TRIP FUNCTION 5 1. R00 SLOCK MON 110R

• Upscale <0.66W+40Ef <0.66W+43k l

! a. liA e b. Inoperative liA

> 5% of RATED THERMAL POWER > 35 of RATED THERMAL POWER

, g c. Downscale U 2. APRM

" Flow Blased Neutron Flux - High < 0.66 W + 42%* < 0.66 W + 45%*

l a. NA 4

b. Inoperative liA i

> 5% of RATED THERMAL POWER > 3E of RATED THERMAL POWER j

c. Downscale

' d. Neutron Flux - Upscale, Setdown i12EofRATEDTHERMALPOWER 514%ofRATEDTHERMALPOWER

3. SOURCE RANGE MONITORS MA NA

a. Detector not full in < 1.0 x 105 cps < 1.6 x 105 cps

b. Upscale liA

c. Inoperative liA ,

> 3 cps ** > 2 cps **

! d. Downscale ,

4. INTERMEDIATE RANGE MONITORS f ,

NA NA

! 1 a. Detector not full in < 108/125 divisions of < 110/125 divisions of I to b. Upscale Tull scale j Tull scale

! NA NA

c. Inoperative > 3/125 divisions of

d. Downscale > 5/125 divisions of.

I"U SC*I' "U '#3I' j 5. SCRAM CISCHARGE VOLUE Water Level-High < 589'11%" < 591'0"

a. liA

b. Scram Trip Bypass liA j

6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW

< 108/125% of rated flow < 111/125% of rated flow

a. Upscale liA y b. Inoperative li4 g c. Comparator i 10E flow deviation i 11% flow deviation j

1. NA NA

7. REACTOR MODE SWITCH SHUT 00WN POSITION il  ? s APRM l

- *TheY rod block function is varied as a function of recirculation loop drive flow (W). The trip setting i of this function must be maintained in accordance with Specification 3.2.2.

l

• • The downscale rodblock setpoint count rate may be reduced to 0.3 cps prior to achieving a burnup of 1 l

' 2000 MWD /T on the first core provided the signal-to-noise ratio is >2. After a burnup of 2000 MWD /T on the first core, the count rate may be reduced to 0.7 cps provided the signal-to-noise ratio is >2.

4 1

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