Text

Proposed Tech Specs Re Acceptance Criterion for Measured RCS Flow Rate for four-loop Operation
	ML20082A764
Person / Time
Site:	Millstone
Issue date:	03/29/1995
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20082A762	List: B15166, Submits Suppl to Original Amend Request on 950124 Re Acceptance Criterion for Measured RCS Flow Rate for four- Loop Operation; ML20082A764;
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	NUDOCS 9504040220
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i Docket No. 50-423 :

B15166 ,

Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Reactor Coolant System Flow Rate Marked-Up Pages ,

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March 1995 l

9504040220 950329 DR ADOCK 05000423 ,

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March 1

.M Qg- , , . i991 TAbtE 2.2-1 ' ,.

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3x REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS , ,

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tC; TOTAL SENSOR g ALLOWANCE ERROR R FUNCTIONAL UNIT (TA) I (S) TRIP SETPOINT ALLOWABLE VALUE

l. Manual Reactor Trip N.A. N.A. N.A. N.A. N.A.

E p 2. Power Range, Neutron Flux

,u

, a. High Setpoint

1) Four Loops Operating 7.5 4.56 0 $ 109% of RTP** $ 111.1% of RTP**

2) Three Loops Operating 7.5 4.56 0 s 80% of RTP** s 82.1% of RTP**

b. Low Setpoint 8.3 4.56 0 1 25% of RTP** s 27.1% of RTP**

l

3. Power Range, Neutron Flux, 1.6 0.5 0 s 5% of RTP** tith 5 6.3% of RTP** with High Positive Rate

a time constant a time constant m 1 2 seconds 1 2 seconds di

4. Power Range, Neutron Flux, 1.6 0.5 0 1 5% of RTP** with 5 6.3% of RTP** with High Negative Rate a time constant' a time constant

, 1 2 seconds 2 2 seconds.

5. Intermediate Range, 17.0 8.41 0 $ 25% of RTP** $ 30.9% of RTP**

i Neutron riux

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'g 6. Source Range, Neutron Flux 17.0 10.01 0 1 10+5 cps i 1.4 x 10+5 cp3 h 7. Overtemperature AT -

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a. Four Loops Operating lg 6- i'l 1' C '

1) Channels I, II 10.0 60- +rH- + - 1.33 See Note 1

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See Note 2 f 5 . 717- Q y + Press)

$ 2) Channels III, IV 10.0 -5 63- -hf+ + 2.60 See Note 1 See Note 2 (Temp + Press) ;

- RTP - RATED THERMAL POWER l

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<. 's March 11, 1991 TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUNENTATION TRIP SETPOINTS U TOTAL SENSOR S ALLOWANCE ERROR 7 FUNCTIONAL UNIT (TA) Z (S) TRIP SETPOINT ALLOWABLE VALUE

b. Three Loops Operating w 1) Channels I, II 10.0 6.80 1.71 + 1.33 See Note 1 See Note 2 (Temp + Press)

2) Channels III, IV 10.0 5.83 1.71 + 2.60 See Note 1 See Note 2 /

(Temp + Press) t -2 9 [

t.c i

8. Overpower AT ( %wlwes omb)4.8 r 3 -k24 -h7P See Note 3 See Note 4 l-

9. Pressurizer Pressure-Low 5.0 1.77 3.3 2 1900 psia 1 1890 psia

10. Pressurizer Pressure-High 5.0 1.77 3.3 s 2385 psia i 2395 psia m 11. Pressurizer Water Level-High 8.0 5.13 2.7 s 89% of instrument S 90.7% of instrument span span

12. Reactor Coolant Flow-Low . 2.5 1.52 0.78 190% of loop 189.1% of loop design flow

design flow

F e 13. Steam Generator Water 18.10 16.64 1.50 118.10% of narrow 117.11% of narrow Level Low-tow l $ g range instrument range instrument span span r+

y 14. General Warning Alarm N.A. N.A. N.A. N.A.

- N .,A .

,w 15. Low Shaft Speed - Reactor 3.8 0.5 0 2 95.8% of rated

! P Coolant Pumps 'l 92.5% of rated speed speed w

w g *MinimumMeasuredFlowPerLoop-66, ourLoopsOperating);(01,066 (Three Loops Operating)-

Vi.kiovwFE'h MS PW fRR - y3 g _gg gcs p:tou paktS m b e \(dea A SetW m 3.t-3-1.-CL RS W d A k (W m ~1.2 3.'2.ct .

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. March 11,11991 4 5 TABLE 2.2-1 (Continued) -

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M -TABLE NOTATIONS (Continued)

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('" ~ NOTE 1: (Continued)

E T' r a 1 587.l*F (Nominal T,yg at RATED THERMAL POWER); p ,

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w K = 0.001311/ psi; 3

Pressurizer pressure, psia;

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P -

P' = 2250 psia (Nominal RCS operating pressure);

S - Laplace transform operator, s 1; and f powerI(AI) rangeisneutron a function of the indicated ion chambers;-with difference gains between to be selected top and based bottom detectors on measured instrumentofresponse the y during plant startup tests such that: s (1) - qb between -26% and + 3%, f (AI) - 0, where q i "d ab are percent RATED THERMAL POWER I Forqktopandbottomhalvesofthecorerespectively,t"dqt+9 in th an b

is total THERMAL POWER in percent of RATED THERMAL POWER; l ,

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(2) For each percent that the magnitude of q, - qs exceeds -26%, the AT Trip Setpoint shall be automatically reduced by 3.55% of its value at RATED -THERMAL' POWER; and 1

t 37 (3) For each percent that the magnitude of q - qu exceeds +3%, the AT Trip Setpoint shall be l@ automatically reduced by 1.98% of its va,ue atT RATED THERMAL POWER. J +

a.

!M ( - L+ %

5 NOTE 2:

s The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than Q ;

,5 AT span (Four Loop Operation); 2.7% AT span (Three Loop Operation).

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10/25/93 ..

Table 2.2-1 (Continued)

TABLE NOTATIONS _iContinued) 1 i NOTE 3: (Continued)

K 6

0.00180/*F for T > T" and K6 - 0 for T 1 T",

T - As defined in Note 1, T" -

Indicated T,q at RATED THERMAL POWER (Calibration temperature for AT instrumentation, 5 587.1*F),

i S - As defined in Note 1, and f(AI) 2

- 0 for all AI.

NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.7% AT span, Crow Loop o pes-no O .

I

NOTE 5: Setpoint is for increasing power.

I NOTE 6: Setpoint is for decreasing power.

NILLSTONE - UNIT 3 2-12 Amendment No. pp,85 es W eTtV h

- *. March 11, 1991

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POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3.2.T;1 'The indicated Reactor Coolant System (RCS) total flow rate and F AH shall be maintained as follows:

3 78

a. RCS total flow rate 2 Mpm,,9%O and N

b. F3H s F3R P [1.0 + PFAH (1.0 - P)]

Where:

THERMAL POWER ,

P =

1) l_ RATED THERMAL POWER N

2) F Measured values of FAH obtained by using the movable ikH core= detectors to tain a power distribution map. The measured value of should be used since Specifica-tion 3.2.3.lb.takesin[o"considerationameasurementuncertainty of 4% for incore measurement, RTP N '

3) F = The F LNITS REPORfH(11mit COLR),. at RATED THERMAL POWER N

4) PF ankg - The power factor multiplier for F3Hprovided in the COLR,

'5) The er.sured value of RCS total flow rate shall be used since uncertainties of 2.4% for flow measurement have been included in Specification 3.2.3.la. /

APPLICABILITY: MODE 1. ,

ACTION:" ;

'With the RCS total flow rate or FfH outside the region of acceptable operation: ,

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

. 1. Restore the RCS total flow rate and F H to within the above limits, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and l I

reduce the Power Range Neutron Flux - High Trip Setpoint to less l than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . ..,

M..ILLSTONE a - UNIT 3 3/4 2-19 AmendmentJJ,#.h

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Docket No. 50-423 B15166 l

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Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Reactor Coolant System Flow Rate Retyped Pages .

March 1995 t-

TABLE 2.2-1 15 ACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS igp TOTAL SENSOR ALLOWANCE ERROR.

3 FUNCTIONAL UNIT fTA) I (S) TRIP SETPOINT ALLOWABLE VALUE E

m 1. Manual Reactor 1+1p N.A. N.A. N.A. N.A. N.A.

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2. Power Range, Neutron Flux

[ a. High Setpoir:t

1) Four Loops Operating 7.5 4.56 0 $ 109% of RTP** 1 111.1% of RTP**

2) Three Loops Operating 7.5 4.56 0 s 80% of RTP** $ 82.1% of RTP**

b. Low Setpoint 8.3 4.56 0 5 25% of RTP** $ 27.1% of RTP**

l 3. Power Range, Neutron Flux, 1.6 0.5 0 5 5% of RTP** with s 6.3% of RTP** with High Positive Rate a time constant a time constant-1 2 seconds 1 2 seconds i m 4, 4. Power Range, Neutron Flux, 1.6 0.5 0 1 5% of RTP** with 1 6.3% of RTP** with High Negative Rate a time constant a time.' constant-1 2. seconds 1 2 seconds

5. Intermediate Range, 17.0 8.41 0 5 25% of RTP** $ 30.9% of RTP**

Neutron Flux

6. Source Range, Neutron Flux 17.0 10.01 0 1 10+' cps 1 1.4 x 10+' cps

] g 7. Overtemperature AT

a. Four Loops Operating E 1) Channels I, II 10.0 8.14. 1.61 + 1.33 See Note 1 See Note 2 y (Temp + Press)

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2) Channels III, IV 10.0 7.17 1.61 + 2.60 See Note 1- See Note 2

?* (Temp + Press) 1 I~ '

. **RTP = RATED THERMAL POWER 4

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. _ . . _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ ~ -, _ _ . _ . _ _ _ . . . . _ . . _ _ . _ _ . _ _ _ _ _ _ _

TABLE 2.2-1 (Continued) o :s REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS ,

TOTAL SENSOR

ALLOWANCE ERROR .

k FUNCTIONAL UNIT (TA) Z (S) TRIP SETPOINT ALLOWABLE VALUE

b. Three Loops Operating

1) Channels I, II 10.0 6.80 1.71 + 1.33 See Note 1 'See Note 2 (Temp + Press)

2) Channels III, IV 10.0 5.83 1.71 + 2.60 See Note 1 See Note 2 (Temp + Press)

8. Overpower AT (Four Loops Operating) 4.8 1.28 1.61 See Note 3 See Note 4 l

9. Pressurizer Pressure-Low 5.0 1.77 3.3 1 1900 psia 1 1890 psia

10. Pressurizer Pressure-High 5.0 1.77 3.3 1 2385 psia 1 2395 psia

11. Pressurizer Water Level-High 8.0 5.13 2.7 s 89% of instrument S 90.7% of instrument span span 4

12. Reactor Coolant Flow-Low 2.5 1.52 0.78 190% of loop 189.1% of loop design flow

design flow *

13. Steam Generator Water 18.10 16.64 1.50 1 18.10% of narrow 117.11% of narrow Level Low-Low range instrument range instrument span span k

g 14. General Warning Alarm N.A. N.A. N.A. N.A. N.A.

E s

15. Low Shaft Speed - Reactor 3.8 0.5 0 1 95.8% of rated 1 92.5% of rated Coolant Pumps speed speed E

D.

D

Minimum Measured Flow Per Lcop - 1/4 of the RCS Flow Rate Limit as listed in Section 3.2.3.1.a (Four Loops Operating);

( 1/3 of the RCS Flow Rate Limit as listed in Section 3.2.3.2.a (Three Loops Operating)

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_ _ _ _ _ _ _ _ . _ _ _ __m , - - _ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _

y '*a y

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TABLE 2.2-1 (Continued)

Q .

k TABLE NOTATIONS (Continued)

NOTE 1: (Continued) h T' 1 587.1*F (Nominal T,yg at RATED THERMAL POWER);

K 3

- 0.001311/ psi; P = Pressurizer pressure, psia; P' - 2250 psia (Nominal RCS operating pressure);

S - Laplace transform operator, s- ;

and f (AI) is a function-of the indicated difference between top and bottom detectors of the 7

'? power-range neutron ion chambers; with gains to be selected based on measured instrument response 5 during plant startup tests such that:

(1) For q, - qb between -26% and + 3%, f,(AI) = 0, . where q and q are percent RATED THERMAL POWER in the top and bottom halves of the core respectively,t and q '+ qb is total THERMAL POWER in percent of RATED THERMAL POWER;

- qs (2) ForeachpercentthatthemagnitudeofqlueatRATEDTHERMALPOWER;andexceeds automatically reduced by 3.55% of its va -26%, the AT Trip Setp (3) For each percent that the magnitude of q - qs exceeds +3%, the AT Trip Setpoint shall be automatically reduced by 1.98% of its vafue at RATED THERMAL POWER.

s g NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 1.4%

AT span (Four Loop Operation); ~d.7% AT span (Three Loop Operation). l g

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_ _ _ _ _ _ . _ . _ .___.____ _ __ _ __ -________m + -- , - . . . 4 - - , . - ,. , , x . .._,w

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h:n TABLE 2.2-1 (Continued) .

M E

m TABLE NOTATIONS (Continued)

E Q NOTE 3: (Continued) u K

6 0.00180/*F for T > T" and K6 - 0 for T 1 T",

T - As defined in Note 1, T" -

Indicated T,yg at RATED THERMAL POWER (Calibration temperature for AT instrumentation, 5 587.l*F),

S - As defined in Note 1, and f 2(AI) - 0 for all AI.

" NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.7% AT span. (Four Loop Operation) l NOTE 5: Setpoint is for increasing power.

l l NOTE 6: Setpoint is for decreasing power.

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- PONER DISTRIBINION LINITS

-3/4 t.3 RCS FLOW RATE AM NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR

-b F0tB LOOPS OPERATING LINITING C0M ITION FOR OPERATION 3.f.3.1 The indicated Reactor Coolant System (RCS) total flow rate and FE shall '

be, maintained as follows:

a. RCS total flow rate 2,371,920 gps, and i

b. F51 Fm" [1.0 + PF, (1.0 - P)]

Where: ;

p, THERMAL POWER yy

< RATED THERMAL POWER, ;

2) FE = Measured values of FE obtained by using the movable incore detectors go obtain a power distribution map. The measured value of Fu should be used since Specification 3.2.3.lb. ,

takes into consideration a measurement uncertainty of 4% for ;

incore measurement,

3) Fm" - The FE limit at RATED THERMAL POWER in the CORE OPERATING g

LIMITS REPORT (COLR), ,

4) PFm - The power factor multiplier for FE provided in the COLR, and

5) The measured value of RCS total flow rate shall be used since uncertainties of 2.4% for flow measurement have been included in Specification 3.2.3.la.

APPLICABILITY: MODE 1. 3 ACTION:

With the RCS total flow rate or FE outside the region of acceptable operation:

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either: -

1. Restore the RCS total flow rate and FE to within the above limits, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Set)oint to less than or equal to 55% of RATED THERMAL POWER wit 11n the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(

NILLSTONE - UNIT 3 3/4 2-19 Amendment No. JJ JJ, JP t' 0181

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ML20082A764

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