ML20044H147

Proposed Tech Specs Tables 2.1-1 & 4.3-1 as Well as Bases 3/4.2.2 & 3/4.2.3 Re Axial Flux Difference Penalty Functions of Overtemperature Delta-T Reactor Trip

ML20044H147
Person / Time
Site:	Callaway
Issue date:	06/04/1993
From:	UNION ELECTRIC CO.
To:
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ML20044H146	List: ML20044H145 ML20044H147
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NUDOCS 9306070473
Download: ML20044H147 (14)

Text

'.p ULNRC-2808

. ATTACHMENT FOUR PROPOSED TECHNICAL SPECIFICATION REVISIONS 9306070473 930604 PDR ADOCK 050004B3 P

PDR

s-

%sd N$

s

-TABLE 2.2-1 (Continued)

E TABLE NOTATIONS 9

NOTE 1: OVERTEMPERATURE AT (y I,,3) $ AT, [K

[T (i f

3) - T'] + K (P - P') - f,(al)}

AT

.K 2

3 t

-e Where:

AT Measured AT

=

l I{

lead-lag compensator on measured AT;

=

Tirs constants utilized in lead-lag compensator for AT, i, s,

t i, T

=

33 s; y

12 <

I Lag Tompensator on measured AT;

=

1+t 5

}

Time constant utilized in the lag compensator for AT, 13 = 0 s;.

13

.=

' Indicated' AT at RATED THERMAL POWER:

AT,

=

K,

.= 1.15; 0.0251/*F; K

=

2 I{

The~ function generated by the lead-lag compensator for T

=

g dynamic compensatlon;-

p m

f.

14, is Time constants utilized in the lead-lag compensator for-T t, # 28 s,

=

3 T

s;

'y Aver 7ge temperature.*F; T.

=

~en -

h I

Lag compensator on measured T,yg;

=

,3 3

O Time constant utilized in the measured T,yg lag compensator, is = 0 s;

.r.

=

u.

~.

G T ABt_E_ 2.,2-1_(Con t i nued )

T ABL E N0_ TAT.l_0J15_ ICpp_t inued).

2

$j NOTE 1: (Continued)

I' 588.4"F (Referenced T at RATED TilERMAL POWER);

g g M

K3 0.00llf;

=

A

/psip P

Pressurizer pressure, psig;

=

P' 2235 psig (Nominal RCS operating pressure);

=

5 Laplace transform operator, s 3 ;

=

and f (al) is a function of the indicated difference between top and bottom detectors of the i

power-range neutron ion chambers; with gains to be selected based on measured instrument

'?

response during plant STARTUP tests such that:

-23%

+/o%,

(1) For qt -9b between -242 and +--f&, f (AI) = 0, where q t and gb are percent RATED TifERMAL l

t POWER in the top and bottom halves of the core respectively, and qt + qb is total THERilAL POWER in percent of RATED TilERMAL POWER;

-23%

P For each percent that g -9 is more negative than -2%/ the oT Trip Setpoint shall (11) t b 4

be automatically reduced by 3.25% of its value.at RATED TilERMAL POWER; 'and l

E

+/o%

j (iii) For each percent that the magnitude of q

-9 exceeds +6t,the aT Trip Setpoint shall t

b be automatically reduced by -12% of its value at RATED Tl!ERMAL POWER.

?

2.9 73 %

M NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3%

b of aT span.

b

I 8w t

TABLE 2.2-1 (Continued)

TABLE NOTATIONS (Continued) 9 E

NOTE 3:

OVERPOWER AT

[

(3f,ag)$AT,(K.-Ks I *fy,5 I],,3) T - K [T (3,

g) - T"] - f (al))

)

I AT g

g 2

v Where:

AT

= Measured AT; l

+ t lead-lag compensator on measured AT;

=

t i. T2 Time constants utilized in lead-lag compensator for AT,

=

1:

8 s.,

t 3 s; Lag compensator on measured AT;

=

y, 3

Time constant utilized in the lag compensator for AT, 1 3 = 0 s;

=

Is Indicated AT at RATED TilERMAL POWER; AT,

=

K, 1.080;

=

7j 0.02/*F for increasing average temperature and 0 for decreasing average K

=

3 g

temperature; ro A

3,f5

'7 The function generated by the rate-lag compensator for T,,

dynamic

=

7 compensation; s-17 Time constant utilized in the rate-lag compensator for Tyg, ty 0 s;

=

h 3,

3 Lag e g ensator on measured T,yg;

=

O Time constant utilized in tiie measured T,yg lag compensator, is = 0 s; re

=

TABLE 4.3-1 (Con'tinued)_

TABLE NOTATIONS

• 0nly if tne P.eactor Trip System breakers he; pen to be closed and the C;ntrol Rod Drive System is capable of rod withdrawal.

!The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outa;e or June 1.1955, whichever occurs first. The provisions of Specificatien 4.0.2 are reset from perfomance of this surveillance.

1. Below P-6 (Inter ediate Range i.eutron Flux interlock) Setpoint.

s e= 5el c., F-10 ( Lea-Settcint Po er F.ange Neutr:n Flux interlock) Setooint.

(1) If not perf:rmed in orevious 31 days.

(2) Com:arison of caloriretric to excore power indication above 15% of RATE:

THERFAL POWER. Acjust excore cnannel cains censistent witn caloritetric power if absolute difference is greater than 2%. Tne provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15; of RATED THERMAL POWER. Recalibrate if the absolute 6 fference is greater than or equal to 4.

The provisions of Specification 4.0.4 are not app.licable for entry nto M3DE 2 or 1.

2 '/o.

(4) Neutron detectors may be excluded from CHANNEL CALI57.ATION.

(5) Cetector plateau curves shall be obtained, evaluated and compared to r.anu-facturer's data. For the Intemediate Range and Power Range Neutron Flux channels tne provisions of Specification 4.0.4 are not applicable for entry into MDDE 2 or 1.

(6) Incore - Excore Calibration, above 75% of RATED THEFyAL POWER. The provi-siens of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

Detemination of the loop specific vessel AT value should be made when perfoming the Incore/Excore quarterly recalibration, under steady state conditions.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

The TRIP ACTUATING DEVICE OPERATI0t1AL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip Attachments of the Reactors Trip Breakers.

~ (8) Deleted (9) Quarterly surveillance in M3 DES 3*,

4*, and 5* shall also include verifica-tion that pemissives P-6 and P-10 are in their required state for existing plant conditions by observation of the pemissive annunciator window.

Quarterly surveillance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.

l CALLAWAY - UNIT 1 3/4 3-12 Amendment No, M, 26

~

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHAlpY RISE HOI CHANNEL FACTOR (Continued)

Each of these is measurable but will nomally only be determined period-ically as specified in Specifications 4.2.2 and 4.2.3.

This periodic surveil-lance is sufficient to ensure that the limits are maintained provided:

a.

Control rods in a single group move together with no individual rod insertion differing by more than + 12 steps, indicated, from the group demand position.

b.

Control rod banks are sequenced with overlapping groups as described in Specification 3.1.3.6.

c.

The control rod insertion limits of Specification 3.1.3.6 are maintained.

d.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.

F will be maintained within its limits provided conditions a. through d.

H N

above are maintained. The relaxation of F as a function of THERMAL p0WER allows changes in the radial power shape fh all permissible rod insertion limits.

When an F measurement is taken, an allowance for both experimental error g

and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full-core map taken with the incore detector flux mapping system and a 3%

allowance is appropriate for manufacturing tolerance.

N When F is measured (i.e., inferred), no additional allowances are g

necessary prior to comparison with the limits of Section 3.2.3.

An error allow-ance of 4% has been included in the limits of Section 3.2.3.

Specifications 3.2.2 and 3.2.3 contain the F and F-delta-H limits appli-g cable to VANTAGE 5 fuel. The OFA fu;l i: :n:1y::d :: 10w;r limit; :in:: it ill have experhnted burnup. thereby reducing th tt:inabh 0F* peci#i: het

-charnel f::ter: :: h that th: cxp :ted p :k p;wer kvch and pt k r:di:1 power 1

--;f th OFA fuel will :: much it;; th n that n;;;;;;ry t: :ppr;;;h th OF^ Fq

-and r-delt: M analy h '4-4tr.

s Margin between the safety analysis DNBR limits-(1.d2 :nd 1.'5 for the Opti-ized fuel thimbh :nd typic 1 ::1h, rc:pecthcly, :nd(1.61 and 1.69 for the VANTAGE 5 thimble and typical cells) and the design DNBR limits (1.33 2nd

-1.35 f:r th Optimi d fu;l thimbi; and typicci ;;1h :nd(1.33 and 1.34 for the VANTAGE 5 thimble and typical cells, respectively) is maintained. A fraction of this margin is utilized to accommodate the tron:ition : r CNSP pen:lty l

1 CALLAWAY - UNIT 1 B 3/4 2-4 Amendment No. J5,28, 44

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

(1255 for ""ME E fud ) and the appropriate fuel rod bow DNBR penalty (4*-/,3%

N '_Et per WCAP-8691, Rev. 1) g The margin between design and safety analysis DNBR limits of C. " for Opti-ince fu;l e M 17.4% for VANTAGE 5 fuel Sc hdx greater ther 2r ergi-f;r hth Cpti-i: d fuel cr.d '/'NC :

ful for plant g

design flexibility.

/.r ava//44/e The hot channel factor F (z) is measured periodically and increased by a cycle and helgnt dependent power factor appropriate to either Nomal Operation or RESTRICTED AFD OPERATION, W(z)NO r W z)RAFD0T to provide assurance that the limit on the hot channel factor, F (z), is met.

W(z)NO accounts for the g

effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core.

W(z)RAFD0 accounts for the more restrictive operating limits required by RESTRICTED AFD OPERATION which result in less severe transient values.

The W(z) functions are specifieo in the Core Operating Limits Report per Specification 6.9.1.9.

Provisions to account for the possibility of decreases in margin to the Fg(2) limit during intervals between surveillances are provided. Any decrease in the minimum margin to the Fg(z) limit compared to the minimum margin detemined from the previous flux map 1s determined by comparing the ratio of:

Fh(z) maximum over z taken from the current map to the same ratio from the previous map. The ratios to be compared from the two flux maps do not need to be calculated at identical z locations.

Increases in this ratio indicate that the minimum margin to the F (z) limit has decreased and that additional penalties must be applied to the Q

measured F (z) to account for further decreases in margin that could occur Q

before the next surveillance. More frequent surveillances may also be substi-tuted for the additional penalty.

3/4.2.4 QUADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distri-bution satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A CALLAWAY - UNIT 1 B 3/4 2-5 Amendment No. 75.2B,44/, 30 e

u INSERT A the flow anomaly penalty (3.3%), the core vs. pressurizer outlet loss coefficient penalty since the core to pressurizer pressure drop is less than 30 psi as assumed in the VANTAGE 5 transition core safety analyses (0.22%), and a penalty (4%) associated with the overtemperature Delta-T AFD penalty function deadband assessed for those events in FSAR Chapter 15 that credit the overtemperature Delta-T reactor trip function.

9 s

i

TABLE 2.2-1 (Continued)

O p

TABLE NOTATIONS 5:

x M

NOTE 1:

OVERTEMPERATURE AT I

AT '1 + T2 )

+ *' '

' +

s ATo{K1-K2 (1 + T5 ) [ T 11 + t6 s

- T* ] + K3 (P - P') - f (AIQ 1

(

S 1 + T3 l S

S S

s i

.8 i

Where:

AT Measured AT;

=

1 + tis Lead-lag compensator on measured AT:

=

g Time constants utilized in lead-lag compensator for AT, ti 2 8 s, t2 s 3 s:

t1, t2

=

1 Lag compensator on measured AT:

=

1 + T3S Time constant utilized in the lag compensator for AT, T3 = 0 s; T3

=

Indicated AT at RATED THERMAL POWER:

AT

=

o K1 1.15;

=

K2 0.0251/ F:

=

+ '#

The function generated by the lead-lag compensator for T

=

avg 1 + TSS dynamic compensation:

Time constants utilized in the lead-lag compensator for Tavg T4 2 28 s, T5 s 4 s:

T4, T5

=

Average temperature, *F; T

=

Lag compensator on measured Tavg;

=

o 1 + T6S c

t6 Time constant utilized in the measured T lag compensator,16 = 0 s:

=

avg ou W

'2l P

O M

s U1

s n

TABLE 2.2-1 (Continued) i TABt E NOTATIONS (Continued)

$z NOTE 1:

(Continued) i T'

5; 588.4 F (Referenced T at RATED THERMAL POWER);

e avg zy K3 0.00116/psig;

=

s P

Pressurizer pressure, psig;

=

2235 psig (Nominal RCS operating pressure):

P'

=

Laplace transform operator, s-1; S

=

and f (AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion 1

chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that:

(i) For qt - Ab between -23% and + 10%, f (AI) = 0, where qt and qb are percent RATED THERMAL POWER in the 1

g 4

top and botom halves of the core respectively, and qt + Ab s total THERMAL POWER in percent of RATED i

THERMAL POWER For each percent that qt - Ab s more negative than -23%, the AT Trip Setpoint shall be automatically reduced by i

(ii) 3.25% of its value at RATED THERMAL POWER: and (iii) Fo. each percent that the magnitude of qt - Ab exceeds + 10%, the AT Trip Setpoint shall be automatically reduced by 2.973% of its value at RATED THERMAL POWER.

g The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3%'of AT span.

NOTE 2:

et 2

P O

s 6'.

O TABLE 2.2-1 (Continued) p TABLE NOTATIONS (Continued)

NOTE 3:

OVERPOWER AT

+ * ' S} '

1

• 7S 1

f AT (1 + T2 )

(1 + T3 s% N-%

T-K6[T

- T" ] - f (AI)}

2

(

S

- S z

s1 + T7S (1 + T6 )

(1 + 16 s S

S e

Where:

AT Measured AT;

=

1 + TSS Lead-lag compensator on measured AT:

=

1 + T2S Time constants utilized in lead-lag compensator for AT, t1 2 8 s, T2 s 3 s; T1, T2

=

1 Lag compensator on measured AT:

=

1 + T3S Time constant utilized in the lag compensator for AT,13 = 0 s; T3

=

Y AT Indicated AT at RATED THERMAL POWER;

=

o o

K4 1.080;

=

K5 0.02/ F for increasing averaga temperature and O for decreasing average temperature:

=

• 7 The function generated by the rate-lag compensator for T

=

avg g

dynamic compensation; Time constant utilized in the rate-lag compensator for Tavg>T7 2 10 s; t7

=

1 Lag compensator on measured Tavg;

=

1 + 16S og 16 Time constant utilized in the measured T lag compensator, t6 = 0 s;

=

avg G

U rt Z

P

• a TABLE 4.3-1 (Continued)

TABLE NOTATIONS

• Only if the Reactor Trip System breakers happen to be closed and the Control Rod-Drive System is capable of rod withdrawal.

1. The specified 18 month frequency may be waived for Cycle i provided the surveillance is performed prior to restart following the first refueling outage or June 1,1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

1. 1. Below P-6 (Intermediate Range Neutron Flux interlock) Setpoint.

1. 1. 1. Below P-10 (Low Setpoint Power Range Neutron Flux interlock) Setpoint.

(1) If not performed in previous 31 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or.1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15%

of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 2%. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

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

(5) Detector plateau curves shall be obtained, evaluated, and compared to manufacturer's data. For the intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

Deteimination of the loop specific vessel AT value should be made when performing the incore/Excore quarterly recalibration, under ~ steady state conditions.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the.

OPERABILITY of the Undervoltage and Shunt Trip Attachments of the Reactor Trip Breakers.

(8) Deleted (9) Quarterly surveillance in MODES 3*,4*, and 5'shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. Quarterly surveillance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.

CALLAWAY - UNIT 1 3/4 3-12 Amendment No. V9,28 i

,o y

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic surveillance is sufficient to ensure that the limits are rnaintained provided:

a.

Control rods in a single group move together with no individual rod insertion differing by more than i 12 steps, indicated, from the group demand position.

b.

Control rod banks are sequenced with overlapping groups as described in Specification 3.1.3.6.

c.

The control rod insertion limits of Specification 3.1.3.6 are maintained.

d.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE,is maintained within the limits.

N F

will be maintained within its limits provided conditions a, through d. above AH N

are maintained. The relaxation of F as a funcdon of WEN NM aHows.

AH changes in the radial power shape for all perrnissible rod insertion limits.

When an Fo measurement is taken, an allowance for both experimental error and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full-core map taken with the incore detector flux mapping system and a 3%

allowance is appropriate for manufacturing tolerance.

N When F is measured ken dene@, no aMonal anowances are necessary 39 prior to comparison with the limits of Section 3.2.3. An error allowance of 4% has been included in the limits of Section 3.2.3.

Specifications 3.2.2 and 3.2.3 contain the Fo and F-delta-H limits applicable to VANTAGE 5 fuel.

Margin between the safety analysis DNBR limits (1.61 and 1.69 for the a

VANTAGE 5 thimble and typical cells) and the design DNBR limits (1.33 and 1.34 for the VANTAGE 5 thimble and typical cells, respectively) is maintained. A fraction of this margin is utilized to accommodate the CALLAWAY - UNIT 1 8 3/4 2-4 Amendment No. V528,44

}

_ POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) appropriate fuel rod bow DNBR penalty (1.3% per WCAP-8691, Rev.1), the flow anomaly penalty (3.3%), the core vs. pressurizer outlet loss coefficient penalty since the core to pressurizer pressure drop is less than 30 psi as assumed in the VANTAGE 5 transition core safety analyses (0.22%), and a penalty (4%) associated with the Overtemperature Delta-T AFD penalty function deadband assessed for those events in FSAR Chapter 15 that credit the Overtemperature Delta-T reactor trip function.

The margin between design and safety analysis DNBR limits of 17.4% for VANTAGE 5 fuelis available for plant design flexibility.

The hot channel factor FM(z)is measured periodically and increased by a cycle O

and height dependent power factor appropriate to either Normal Operation or RESTRICTED AFD OPERATION, W(z)NO or W(z)RAFDO, to provide assurance that the limit on the hot channel factor, Fo(z), is met. W(z)NO accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)RAFDO accounts for the more restrictive operating limits required by RESTRICTED AFD OPERATION which result in less severe transient values. The W(z) functions are specified in the Core Operating Limits Report per Specification 6.9.1.9.

Provisions to account for the possibility of decreases in margin to the Fo(z) limit during intervals between surveillances are provided. Any decrease in the minimum margin to the Fo(z) limit compared to the minimum margin determined from the previous flux map is determined by comparing the ratio of:

'M maximum O

over z s K(z) s taken from the current map to the same ratio from the previous map. The ratios to be compared from the two flux maps do not need to be calculated at identical z locations. Increases in this ratio indicate that the minimum margin to the Fo(z) limit has decreased and that additional penalties must be applied to the measured Fo(z) to account for further decreases in margin that could occur before the next surveillance.

More frequent surveillances may also be substituted for the additional penalty.

3/4.2.4 OUADRANT POWER TILT RATIO The OUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A CALLAWAY - UNIT 1 B 3/4 2-5 Amendment No. YS, 28,44,58