ML20132G405

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs 3.3.1.1,Table 4.3.1 Re Power Calibr Requirements
ML20132G405
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/19/1996
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20132G387 List:
References
NUDOCS 9612260250
Download: ML20132G405 (7)
v • d • e


Text

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

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

n  ?

p 5

, i 4

4 4- ,

s  :

d I

.- t i

i 4-4 a

?

.t I

s 4  !

I b,

-l, I l t

3 i

^

5 J

e T

PROPOSED TECHNICAL SPECIFICATION CHANGES i

i i

i. .

5

, s l

l  !

1 t t

-t I

i 9

9612260250 961219 POR ADOCK 05000369 P PDR

1 l

TABLE 4.3-1 (Continurd)

. TABLE NOTATIONS j With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.  !

(1) -

If not performed in previous 7 days.

l (2) -

Heat balance only (CHANNEL FUNCTIONAL TEST not included): '

a. Between 15% and 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC AT power, and the CPC nuclear power signals to the calorimetric calculation.

I i If any signal is within -0.5% to +10% of the calorimetric calculation, then do not calibrate except as required during initial power ascension following refueling.

If any signal is less than the calorimetric calculation by more j than 0.5%, then adjust the affected signal (s) to within 0.0% to

+10.0% of the calorimetric calculation.

If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal (s) to within 8%

to 10% of the calorimetric calculation. i f

b. At or above 80% of RATED THERMAL POWER, compare the Linear Power ,

Level, the CPC AT power, and CPC nuclear power signals to the  !

calorimetric calculation. If any signal differs from the

calorimetric calculation by an absolute difference of > 2%, j then adjust the af fected signal (s) to within i 2% of the l

calorimetric calculation. '

i l During PHYSICS TESTS, those 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 l l subchannel gains of the excore detectors are consistent with the i values used to establish the shape annealing matrix elements in l 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 I THERMAL POWER, the incore detectors shall be used to determine i the shape annealing matrix elements and the Core Protection l Calculators shall use these elements.

l (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.

l ARKANSAS - UNIT 2 3/4 3-8 Amendment No. G4,39,M ,

, a

, (7) -

Abova 706 of RATED THERMAL POWER, varify that the total RCS flow rato na indic: tad 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 (conservatively compensate for measurement uncertainties) or by calorimetric calculations (conservatively compensated for measurement uncertainties) 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 BERR1 term in the CPC and is equal to or greater than 4%. l (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 (conservatively compensated for measurement uncertainties).

(9) -

The correct values of addressable constants shall be verified to be installed in each OPERABLE CPC.

l

)

i I

ARKANSAS - UNIT 2 3/4 3-9 Amendment No. G4, 39, -74, l

i

0 e e

e I

i l

MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFO ONLY) i l

I

\

l l l

l r

5 1

4

i - .

TABLE 4.3-1 (Centinurd)

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

(1) -

If not performed in previous 7 days.

(2) -

Heat balance only (CHANNEL FUNCTIONAL TEST not included)

a. Between 15% and 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC AT power, and the CPC nuclear power sianals to the calorimetric calculation.

If any slanal is within -0.5% to +10% of the calorimetric calculation, then do not calibrate except as recuired durina initial power ascension followina refuelina.

If any sianal is less than the calorimetric calculation by more than 0.5%, then adiust the affected sianal(s) to within 0.0% to

+10.0% of the calorimetric calculation.

If any sianal is creater than the calorimetric calculation by more than 10%, then adiust the affected sional(s) to within 8%

to_10% of the calorimetric calculation.

b. At or above 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC AT power, and CPC nuclear power siapals to the calorimetric cAJculation. If any sianal differs from the calorimetric calculation by an absolute difference of > 2%,

then adiust the affected sianal(s) to within i 2% of the calorimetric calculation.

, bev: 15 . Of PJ.T4B-THEP".".L POWEn; adj ust the Lines: Pou :

Level cignal: :nd the CPC addeescable constant multipli::: to mah the CPC--AT peuer and CPC nucles: peu : :1 ulation ag:::

with th Oslerimetrie : lcul tion if Ob: lut; difference i 12S.

During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major i

test power plateau and prior to proceeding to the next major test i power plateau.

(3) -

Above 15% of RATED THERMAL POWER, verify that the linear power l subchannel gains of the excore detectors are consistent with the l values used to establish the shape annealing matrix elements in l

the Core Protection Calculators.  ;

(4) -

Neutron detectors may be excluded from CHANNEL CALIBRATION.

I (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 i sensors as practicable to verify OPERABILITY including alarm j and/or trip functions.

ARKANSAS - UNIT 2 3/4 3-8 Amendment No. G4, 39, -74,

_ .i i

l l

i i

.6 . l l

. (Th7 infermatien en thin p*ge will be pleced en p go 3/4 3-9) i i

  • ., _._t _.._ ., n,, a , , . n

,en

..u.,.,.n..m..,. m m_., e n , ....., .t.. . .t.._

... . n...., ... ,,._.

.m,.

...,2..,_.._.m.__., .. t,.. ...t.. ,n.

m.t.._._. , , . _.,_

_.__,. m.,, ..t.._ -,m.._.,. __ _,

n,o. .e. .,_&.._.,. . . . - - .. _.. .a.. . ._._,__2 t,.. ..t.._.._ . . _ , _ _ .

..t.._ ....___ __

u. s..a_ . _ ...

_ u. .s _, _____

7...,._.__. ...__u.._...___u._,__. . . .

_ _ _ , _ _, , , , . . . ..y_._.,

,______....2._,.. _ ,_

, , , , , . . . . . . . . . . . , _______...y... m.. ____._._____m. ..____m.._.,_.,__1

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

.. t.,,.. ,

__,_J.~_mJ_.. ,,_...1._.6..J._.__

m....,..._s....1.. .

......y....s...J . . .

s_ j

_ _ _ . . . . . ~ . . . . . . ..____u.. int.,__.,s .. .__. . , . , .a _______

.e ... . . ,.., ..u._._

_; .t..._ ,, n. n i

_.a,a. .... ,_ ____.

u.. ,,,,. ... . _._ .., ,._ ,. _ . ___,,,_,__

..,t.. .t..._.. ,,_,t.. ,, .n .

l

...2..,._.._._2 .. . . , ,

,,_._. 2._. ,___ ..

.... .t.._._. . .. . , _ ,.. .,

.t..._ . . . . _ ,.. . . . , . _ . .

m. .
m. t. . .

s.,._,._.

. . , . . . . . ~ . . . ...____6.._..,6...

. . . . . , .. ,.. t,._ J._._.,..J..J .J _..

. . .. s.t..._ n

. e. n.

. ..n, .t l

. . . . . . . . .t..._.

. ,,n.,

...,2

. _,s#, my

. - . ,,_.___ __ m.t...__. u. . . . ... .

i

.f .o ,i .m_u,...,,

. ', h, n. , - .s

. n. .s.. m. .e.n., m.. u.. e.# ..m.t n,st , e.n. , . .. ....J s,. . a u. . ._ 6 a.t..,_. s.._m.._., .n. .e, .s.,._,._.

t..

, ._ _ sr.t. . .. , n o.

.. .... ..t..__. .. _ _. . ,. .. ...

m.t. . _ . , , . _ . ,.

n,,, e

.,. .. ._6. i.. .s..._. _ , _ _ J

_6.._. .J. ,_A. . . . . . . . u.,.. ._.m..._6.J._ __, _, .~ . _ .....,_aJ_ _ , _.. . ...

t______.._2..,..

,. .- . .y . .a .,i _..J. .E._. ..-_..-___L. .. ._. _. _. . . .. ..J _ L.2 ._ ,,i .

m....... ....., . .. . , - . .

-( n., ,t .t..._ . .. . . . . . , .. _,a.,.i._._._.._.._.u.s._ _ _ ____ __ _

. . . . . . . _t..._.,, .. t ._ . .......

_ 4 , 4 ._ .;. . , _.,

u. ._ ....,.i.,.m,J .J ._ ___ ..t. ,. , ,% . n.e n. ,.h.n. .. ,.,,.

,,n,,

4 l

l l

i 1

i 1

.i l

1 1

4 f

I 4

1 1

1 1

l l

J i

i ARKANSAS - UNIT 2 3/4 3-8 Amendment No. 34,49,4-7, l

e *

. (7) -

Above 70% of RATED THERMAL POWER, verify that the total RCS flow Late as indicated by each CPC is less than or eaual to th.e actual

, RCS total flow rate determined by either usino the reactor coolant pump dif ferential pressure instrumentation (conservatively compensate for measurement uncertaintles) or by calori_ metric calculations (conservatively compensated for measurement uncertainties) and if necessary, adiust the CPC addressable constant flow coefficients such that each CPC ,

indicated flow is less than or ecual to the actual flow rate.  !

The flow measurement uncertainty may be included in the BERR1 Lerm in the CPC and is eaual to or creater than 4%.

I (8) -

Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate aE_ indicated by each CPC is less than or eoual to the actual  ;

RCS total _ flow rate determined by calorimetric calculations I (conservatively compensated for measurement uncertainties).

(9) -

The correct values of addressable constants shall be verified to l Q ,in.-tay.ed in each OPERABLE CPC.

)

I TRIC CACC LEET SLANN INTENTION"LLY l l l

l

)

i i

i ARKANSAS - UNIT 2 3/4 3-9 Amendment No. G4, 49, M,

Retrieved from "https://kanterella.com/w/index.php?title=ML20132G405&oldid=2884042"