Text

Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs
	ML20134K998
Person / Time
Site:	Sequoyah
Issue date:	02/07/1997
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
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	NUDOCS 9702180108
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i s.

1 t

ENCLOSURE 1 4

i REVISED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-96-01, REVISION 1) j

~

i LIST OF AFFECTED PAG'ES 4

3 i

4 Unit 1 3/4 2-10 (Insert G) 3/4 2-11 (Insert G)

Unit 2 a

3/4 2-8 (Insert G) 3/4 2-9 (Insert G) 9702180108 970207 PDR ADOCK 05000327 P

PDR

e I.

fist POWER DISTRIBUTION LIMITS 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR - F g (%.Y)

[^

~

4 LIMITING CONDITION FOR OPERATION I

3.2.3 T

Nucle Enthal Hot Cha 1 Factor F s

1 be li ed by th R142 AH folio,ng rel onship:

RP gg 5, F

.0 + PF (1.0-P k

T MAL POW R159 wh P=R D THERM POWER '

RT F

= The F limit t RATED T RMAL POWE (RTP) specif" d in the f,b C

R, and fL PF The p er factor ultiplier rF speci ed in the COL.

g Ifb APPLICAB1LITY:

DE 1 1

A V

r N

Wi F

exc. ding its it:

g a.

educe TH L POWER t ess than 5 f RATED THE L POWER wit '

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months nd reduce t Power Range eutrea Flux-gh Trip Setp nts to 5

% of RATED ERMAL POWER thin the ne 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

[

l N

b.

monstrate ru in-core m ping that F is within it imit within 2 ours after ceedira the mit or reduc HERMAL PO to les than 5% of ED THERMAL P ER within t next 2 hou

, and c.

I ntify and c rect the cau of the out limit con

ion prior o increasi THERilAL POW above the re ced limit quired by a cr b. abo

subsequent WER OPERATI may proce provided t Fhidemonstrated rough in-co mapping t "oe within i limit a a nominal 5 of RATED THE L POWER pr r to exce ng this HERMAL POWE at a nominal '/5% of RATE HERMAL PO prior exceeding is THERMAL P R and wit 'n 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ter att ' ing

[

95% or ater RATED T RMAL POWE SEQUOYAH - UNIT 1 3/4 2-10 Amendment No. 19, 138, 155 00i n El

g.

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POWER DISTRIBUTION LIMITS

')

SURVEILLANCE REOUIREMENTS

a f-6 2

.1 ep vision f Specif ation 4.0.

are not aa icable.

4.2

.2 sha be dete. ned to be thin its mit by usi the mova g

k cor detect s to obt n a power stributto ap:

/. a.

rior t operation ve 75% of TED THERM POWER aft each el lead

, and b./ least on per 31 Ef etive Full ower Days.

R142 i

Th u dF all be in ased by or mea rement N

t NN 0 h. ]0SQ SEQUOYAH - UNIT 1 3/4 2-11 Amendment No. 138 i

I i

G INSERT G i

FasM,Y) shall be maintained within the limits specified in the COLR.

i APPLICABIL'~Y: MODE 1 i

i ACTION:

)

With Fas(X,Y) exceeding the limit specified in the.COLR:

i

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

i

1. Restore F s(X,Y) to within the limit specified in the COLR, or a

2. Reduce the allowable THERMAL POWER from RATED THERMAL POWER at least RRH*% for each 1% that F s(X,Y) exceeds the limit, and 3

b. Within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

j

1. Restore F s(X,Y) to within the limit specified in the COLR, or 4

3

2. Reduce the Power Range Neutron Flux High Trip Setpoint in Table 2.2-1 at i

least RRH'% for each 1 % that Fas(X,Y) exceeds that limit, and

c. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the limit specified in the COLR, either:

)

1. Restore Fas(X,Y) to within the limit specified in the COLR, or j

2. Verify through incore flux mapping that F s(X,Y) is restored to within the 3

limit for the reduced THERMAL POWER allowed by ACTION a.2 or reduce j

i THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

i

RRH is the amount of power reduction required to compensate for each 1 % that F s(X,Y) exceeds the limit provided in the COLR per Spec:fication 6.9.1.14.

3

1 o

. ACTION: (Continued)

d. Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of initially being outside the limit specified in the COLR, reduce l

the Overtemperature Delta T K, term in Table 2.2-1 by at least TRH*

for each 1 % that Fan (X,Y) exceeds the limit, and

e. ' identify and correct the cause of the out-of-limit condition prior to increasing l

THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2 and/or b. and/or c. and/or d., above: subsequent POWER OPERATION may proceed provided that Fas(X,Y) is demonstrated, through l

incore flux mapping, to be within the above limit prior to exceeding the following THERMAL POWER levels:

j

1. A nominal 50% of RATED THERMAL POWER,

2. A nominal 75% of RATED THERMAL POWER, and

3. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED

' i THERMAL POWER.

i i

TRH is the amount of Overtemperature Delta T K, setpoint reduction required to compensate for each 1 % that Fas(X,Y) exceeds the limit provided in the COLR per Specification 6.9.1.14.

t 9

l

4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 F"JX,Y) shall be evaluated to determine if Fas(X,Y) is within its limit by:

3 Using the movable incore detectors to obtain a power distribution map F"JX,Y)

a.

3 at any THERMAL PCWER greater than 5% of RATED THERMAL POWER.

b. Satisfying the following relationship:

FAHR"(X,Y) s BHNOM(X,Y)

Where:

F "(X,Y)

FA HR "(X, Y) =

MAP " I AXIAL (X,Y)

And BHNOM(X,Y)' represents the nominal design increased by an allowance for the expected deviation between the nominal design and the measurement.

s MAP" is the maximum Allowable Peak'* obtained from the measured power distribution.

AXIAL (X,Y) is the axial shape for F sW,W.

3

c. If the above relationship is not satisfied, then

1. For the location, calculate the % margin to the maximum allowable design as follows:

FAHg*6(p),

,M gv,,

%F Margin 1-x 100 %

3n BHDES (X, Y),

r BRDES 4 Y, X lDOYo o/dj(4/)/T]ARCIN.:

.1-where BHDES(X,Y)' r,epresentf the(max)imum allowable design peaking

]

factor 3which insur i that the licensing criteria will be preserved for operation within the LCO mits, and include / allowances for calculational and measurement ancertainties.

/so BRDES (xyy No additional uncertainties are required in the following equations for F3u(X, Y) 2 Avo

/M#R [ )/),because the limits include uncertainties.

gjpM

/6vo BRDEs(X,Y)/

^

BHNOV(X,Y).amkBHdES(X Y[ data bases are pr 'ded for input to the plant i

q p'owerhnalysis co r co es on a cycle specific basis and are j

determined using the methodology for core limit generation described in tlie references in Specification 6.9.1.14.

4

3. If my4 margin in 4.2.3.2.c.2 above is < 0,greduce the allowable THERMAL POWER from RATED THERMAL POWER by RRH* % x most negative margin from 4.2.3.'! c.2 and maintain the requirements of Specification 3.2.3; otherwise the Action statements for 3.2.3 apply.

~

d. With two measurements extrapolated to 31. EFPD beyond the most recent measurement yielding I

FAHR"(X,Y) > BHNOM(X,Y) either of the following actions shall be taken:

S 1.

F"JX,Y) shall be increased over that specified in 4.2.3.2.a by the 3

repeated, or

2. F"JX,Y) shall be evaluated according to 4.2.3.2 at or before the time when 3

tgrga in i projected to result in the action specified in 4.2.3.2.c.3g 04 4.2.3.3 F$(X,Y) shall be determined to be within its limit by using the incore detectors U t in a power distribution map:

a. Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and 4

b. At leact nnce oer 31 EFPD-e h Tx?fj (hfll$kecar To '/z.s.2.c.2 Aton 1s 4 0,TseN U/UN^'

</t //oyks japuts THE OfC&7El!l?fNAIU55 A

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$2.3.2.c.2 jpo By Ar Lenst 7RH H 0/o / /AM7-Alr4ADW AnxC/^/

CM thwrM/N THE ACQui/EMEh?T3 Of S/EC/f/ CAT /oD 12. h* 0THERhhst ThW iknoiv 3rgrrnw73 Jix 3. g. 3 Arn)'.

n

RRH is the amount of power reduction required to compensate for each 1 % that Fa mit provided in th pecificatig1.14.

M TRH.Is Txe 19mpusr or Gnwrirrst'exn7uxe De2ryg 7 Xj SerroiNr

$CDt/CT70/U ODut/ED % fem /Lc?vs/17E & [AcH.1 *f 7p'47 f, (x,y)

Exeans Tae tiiriir Regioco.TN Txe totR Ibe Speoriesrio'U 5.7/.lf.

IFu so tristciw= pfwy,,,,,, y; giixgiis (guie. g, ga jseg7,ow, kweo.

lJi ai) riau tiesw = idwimum % 14sxcw fauc or Au. Lo

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RIS' POWER DISTRIBUTION LIMITS 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR Fu b.d f '.

~

LIMITING CONDITION FOR OPERATION R130

_ 3. 2. 31 dheNucl r Enthalpy ot Channe Factor, shall e limite by the g

wing rel 1onship:

F F

[1. 0 PFg (1. -P)]

j H

l THERMAL OWER R146 where P = RATED TH L POWE TP = Th limit t RATED T RMAL P0 (RTP) sp cified in e

g k*

LR, and PF

- The pow factor m tiplier rFhspe fied in t

COLR, 3

V APPLICAB ITY: MO 1

ACTI N

ith F xceeding

s limit:

g Reduce ERMAL P R to less han 50% o RATED THE L POWER wi in 2 ho s and re ce the Pow Range Ne ron Flux-h Trip Se oints to 55% of R ED THERMA POWER wit n the next

hours, R/30 b.

emonstra thru in-re mappin thatFhiwithinits imit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months af er exceed g the limi or reduce ERMAL POWER to 1 s than 5%

RATED T MAL POWER ithin the xt 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , nd c.

I ntify and orrect th cause of e out of 1 it conditio prior oincreas'gTHERMAL/0WERabov he reduce limit requir d by a.

/

or b. ab e; subse utnt POWER 0 RATION ma proceed pro ded that Fhidemonstra d through

-core map :ng to be wi in its limi at nominal of RATED HERMAL P0 prior to ceeding thi T RMAL POW, at a nom al 75% of TED THERMA OWER prior o xceeding is THERMA POWER and ithin 24 ho s after att ning

/

95% or ater RATE HERMAL P0 R.

/

~

SEQUOYAH - UNIT 2 3/4 2-8 Amendment No. 21, 130, 146 March 30, 1992

POWERDISTRIBETIONLIMITS SURVEILLANCs REQUIREMENTS g

pr ons of Speci on 4.0.4 ar applicab 4.2.

shall be reined to b in its 1 y usin ovable g

y core date to obtain wer distr on map:

Prior ration a

% of RAI ERMAL PO er each fuel u30 ng, 6 once Effective ower Days, an b.

At The red F e increased b or measurement N

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uncert y

/

i SEQUOYAH-dNIT2 3/4 2-9 Amencment No.130 OCT02.,.M

INSERT G F s(X,Y) shall be maintained within the limits specified in the COLR.

i APPLICABILITY: MODE 1 ACTION:

With F s(X,Y) exci.s "ng ti1e limit specified in the.COLR:

6

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

1. Restore Fas(X,Y) to within the limit specified in the COLR, or

2. Reduce the allowable THERMAL POWER from RATED THERMAL POWER at least RRH* % for each 1 % that F s(X,Y) exceeds the limit, and a

b. Within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1. Restore Fas(X,Y) to within the limit specified in the COLR, or

(

2. Reduce the Fnwer Range Neutron Flux-High Trip Setpoint in Table 2.2-1 at least RRH'% for each 1 % that Fas(X,Y) exceeds that limit, and

c. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the limit specified in the COLR, either:

1. Restore F s(X,Y) to within the limit specified in th* COLR, or 6

2. Verify through incore flux mapping that Fas(X,il is restored to within the limit for the reduced THERMAL POWER allowed by ACTION a.2 or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

RRH is the amount of power reduction required to compensate for each 1 % that Fasm,Y) exceeds the limit provided in the COLR per Specification 6.9.1.14.

I l

+

4 ACTION: (Continued)

o. Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of initially being outside the limit specified in the COLR, reduce the Overtemperature Delta T K term in Table 2.2-1 by at least TRH for each i

1 % that Fas(X,Y) exceeds the limit, and 4

e. Identify and conect the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2 and/or b. and/or c. and/or d., above: subsequent POWER OPERATION may proceed provided that F (X,Y) is demonstrated, through as incore flux mapoing, to be within the above limit prior to exceeding the following i

THERMAL POWER levels:

l

1. A nominal 50% of RATED THERMAL POWER,

2. A nominal 75% of RATED THERMAL POWER, and

3. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

l s

i TRH is the amount of Overtemperature Delta T K setpoint reduction required to 3

compensate for each 1 % that Fas(X,Y) exceeds the limit provided in the COLR per Specification 6.9.1.14.

l I

l l

a-i

' i 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

[

f 4.2.3.2 F"JX,Y) shall be evaluated to determine if Fas(X,Y) is within its limit by:

t 3

l l

a. Using the movable incore detectors to obtain a power distribution map F"JX,Y)

3 at any THERMAL POWER greater than 5% of RATED THERMAL POWER, t

b. Satisfying the following relationship:

FAHR"(X,Y) s BHNOM(X,Y)

Where:

F[(X,Y)

FA HR "(X, Y) =

MAP " l AXIAL (X,Y) l And BHNOM(X,Y)*

represents the nominal design increased by an allowance for the expected deviation between the nominal design and the measurement.

o MAP" is the maximum Allowable Peak'* obtained from the measured power distribution.

AXIAL (X,Y) is the axial shape for F s(X,Y).

i

c. If the above reladonship is not satisfied, then

1. For the location, calculate the % margin to the me.ximum allowable design as follows:

i FAHR ^hGd, P*

/ *> tA

%F Margin 1-x 100 %

3g BHDES (X,Y),

r

'Y BRDES 4Y, X lDOYo of,& (4/)/1MACIN =

.t~

where BHDES(X,Y)*

represent / the(max)imum allowable design peaking factor 5which insur 4 that the licensing criteria will be preserved fur operation within the LCO mits, and include / allowances for calculational and measurement neertainties.

/so uns (x,yy No additional uncertainties are required in the following equations for F"u(X,Yb AND 3

/~AY,Y),because the limits include uncertainties.

(-

M

/fWo BRDES(4Y)/

_ B_HNOM(X,Y BHdES(

ata bases are pr 'ded for input to the plant power distribu ysis co r codes on a cycle specific basis and are determined using the methodology for core limit generation described in the references in Specification 6.9.1.14.

^

l, 4

F margin of alllocati ex 1 above.

fy-

'Tae fa the Tatw 4)ml!N 2 HouAs i

3. If a w amargin in 4.2.3.2.c.2 above is < 0,greduce the allowable THERMAL POWER from RATED THERMAL POWER by RRH'% x most negative margin from 4.2.3.2.c.2 and maintain the requirements of Specification 3.2.3; otherwise the Action statements for 3.2.3 apply.

d. With two measurements extrapolated to 31. EFPD beyond the most recent measurement yielding FAHR"(X,Y) > BHNOM(X,Y) i 4

either of the following actions shall be taken:

1.

F"JX,Y) shall be increased over that specified in 4.2.3.2.a by the 3

appropriate factor specified in the COLR, and 4.2.3.2.c.1 repeated, or 2.

F"JX,Y) shall be evaluated according to 4.2.3.2 at or before the time when 3

tgagin i projected to result in the action specified in 4.2.3.2.c.3g 04:

4.2.3.3 F$(X,Y) sing the incore i

detectors t

n a power distribution map:

a. Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and

b. At lent nnce ner 31 EFPrt si(h//w 1Alcia.To Yz.3.2.c.2 Asoa.1s 4 0,Tseu 4.hnar' 4 Is Tot de //ouas fepute Ta Ordmn!RATaxe ba,8 T X Texx.tv Tsmi 2.2.1 i

I Y2*3 2 c 2 Ano By Ar Lensr 7Rll" % / Dlar A!'AT'" A""' &#"

/Inwrxis Txe AcQudCMENr3 Of b/Elif/ CAT /oM 3.2.3j 0THMW1.st TM j

Acrion 3rn7tMsn>75 fix 3.2. 3 APAf.

i j

m

RRH is the amount of power reduction required to compensate for each 1% that F, (X,Y) exceeds the limit orovided in the COLR per Specific %ation 6 9.1.14.

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$EDut770/V $ Equi /ED To (tyrjpLc79.S,975-Qg [gcy _f % 7,,77 f (yy Execas Tie Limir Beopem L Txe COLA /En 6/wmMT/o Mw ristois. y/mii,,,,,, % Mnxsiid Ynwe- & Aa lsesricas Eastwen F,g h(si) etw Mnesw = Mwimum % Mnwa faur Or Au.

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ENCLOSURE 2 q

REVISED ' TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 l

DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-96-01, REVISION 1)

DESCRIPTION AND JUSTIFICATION FOR THE CONVERSION FROM WESTINGHOUSE ELECTRIC CORPORATION FUEL TO FRAMATOME COGEMA FUEL (FCF) (MARK-BW17) 9

}

l i

Descriotion of Chance TVA proposes to modify the Saquoyah Nuclear Plant (SON) Units 1 and 2 technical specifications (TSs) and to revise the original TS change request. This revision will add a percent f (AI) Margin calculation and associated changes to proposed Surveillance i

Requirement 4.2.3.2.c and includes a revised term from the original submittal.

Footnotes associated with Surveillance 4.2.3.2 have been revised as necessary.

Surveillance Requirement 4.2.3.2.d has been revised to reference the f (AI) Margin i

i actions added to Surveillance 4.2.3.2.c.

Beason for Chance During the TVA review of the core analysis computer codes being used in conjunction j

with the original TS change request, the need for a revision to provide clarity to the

)

new TS wording was identified. This computer code provides a printout of actions to I

follow in the event surveillance limits are exceeded. The actions that were indicated for hot channel factors exceeding surveillance limits were not crimpletely consistent with the proposed TS requirements for these conditions. As a result of extensive reviews of code test data, TVA identified areas of the codc output that did not match well with the originally proposed TS change. Using SON specific information, the code outputs were evaluatad to ensure appropriate actions were indicated. TVA has coordinated with Framatome Cogema Fuels to determine the appropriate TS surveillance requirements that will match the outputs provided by the core analysis computer code. The code methodology has not changed. This revision to the original TS change reque w will ensure consistency in the application of TS requirements when I

hot channel factor limits are exceeded.

Justification for Chanaes These revisions to the originel TS change request affect pages associated with the power distribution limits in TS section 3/4.2.3, Nuclear Enthalpy Rise Hot Channel Factor - F-delta H(X,Y). This change provides recognition in the TS requirements that there are two ways in which the core analysis code MONITOR treats the F-delta H hot channel factor to address safoty analysis assumptions. The first consideration is DNB for initial conditions at the time of limiting transients such as loss of reactor coolant system flow. The second consideration is DNB during steady-state operations to preserve safety limits for fuel centerline melt requirements. These revisions do not reflect a change in the methodology of the core analysis code but do provide more accurate TS actions associated with hot channel factor limits and the code output. The revised TS actions recognize code outputs that were not included in the original TS change request. The original evaluations for this TS change request continue to be valid because the analysis is unchanged and the impact to the plant is the same as originally described.

Environmental imoact Evaluation The proposed change does not involve an unreviewed environmental question because operation of SON Units 1 and 2 in accordance with this change would not:

1.

Result in a significant increase in any adverse environmental impact previously I

evaluated in the Final Environmental Statement (FES) as modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmentalimpact appraisals, or decisions of the Atomic Safety and Licensing

Board, 2.

Result in a significant change in effluents or power levels.

3.

Result in matters not previously reviewed in the licensing basis for SON that mcy have a significant environmental impact.

i l

1 1

g

~

ENCLOSURE 3 REVISED TECHNICAL SPECIFICATION CHANGE

)

SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON TS-96-01, REVISION 1)

]

REVISED DRAFT CORE OPERATING LIMITS REPORT SUPPORTING THE CONVERSION FROM WESTINGHOUSE ELECTRIC CORPORATION FUEL -

TO FRAMATOME COGEMA FUEL l-AFFECTED PAGES l

Pages 5 and 6 of 12 1:

0 I

l ll

s

DRAFT COLR IVR SEQUOYAB UNIT 1 CYCLE 9 BQNOM(X,Y,Z), BQDES(X,Y,Z), and BCDES(X,Y,Z) data bases are provided for input to the plant power distribution analysis codes on a cycle specific basis and are determined using the methodology for core limit generation

?

described in the references in Specification 6.9.1.14.

M 2.5.10 All cycle burnups shall use a 2% increase in Fg (X, Y, Z) margin r

for compliance with the 4.2.2.2.e Surveillance Requirements.

2.6 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) j (Specification 3/4.2.3)

FAH(X,Y) shall be limited by the following relationship:

f FAH(X,Y)

< MAP (X,Y,Z) / AXIAL (X, Y) t J

2.6.1 MAP (X,Y,Z) is provided in Table 1 for Mark-BW fuel and f

Westinghouse fuel.

i AXIAL (X,Y) is the axial peak from the normalized axial power l

shape.

']

1

/..

The following parameters are required for core monitoring per the Surveillence Requirements of Specification 3/4.2.3:

J PAHRM(X,Y)

< BHNOM(X,Y) where FAHRM(X,Y) =FAH (X, Y) / MAPM / AXIAL (X,Y)

FAH(X,Y) is the measured radial peak at location X,Y.

MAPM is the value of MAP (X,Y,Z) obtained from Table 1 for the measured peak.

2.6.2 BHNOM(X,Y) = nominal design radial peaking factor, increased by an allowance for the expected deviation between the nominal design power distribution and the measurement.

2.6.3 BHDES(X,Y) = maximum allowable design radial peaking factor which ensures that the FAH(X,Y) limit will be preserved for operation within the LCo limits, including allowances for calculational and measurement neertainties.

W BHNOM(X,Y),end BHDES (X,Y)(Asso BRDE3 (f b

~

data bases ar provided for input to the plant power distribution analysis c.

er codes on a cycle specific basis and are determined using the methodology for core lindt generation described in the references in Specification -

jgzy 6.9.1.14.

a SEQUOYAH - UNIT 1 Page 5 of 12 Revision 0

-~

4' I

insert 4

l 1

2.6.4 BRDES (X,Y) =

maximum allowable design peaking factor which ensures that the steady-state DNBR limit will be preserved for

]

operation within the LCO limits, including allowances for calculational and measurement uncertainties.

i i

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(

DRAFT COLR ICR-SEQUOYAH t' NIT 1 CYCLE.9 l

y

)

2. 6.j( RRH = - 3. 34 when 0. 8 < P < 1. 0

+

RRH = 1. 67 when P <. 0. 8 l

where RRH = Thermal power reduction required to compensate for i

each 1% that FAH(X,Y) exceeds its limit.

i P = Thermal' Power / Rated Thermal Power 2.6.

TRH = 0. 033 when 0. 8 < P < 1. 0

(

TRH = 0.017 when P < 0.8 I

where TRH = Reduction in OTAT K1 setpoint required to compensate for each 1% that FAH (X, Y) exceeds its limit.

2.6./ All cycle burnups shall'use'a 2% increase in FAH (X,Y) for M

compliance with the 4.2.3.2.d.1 Surveillance Requirement.

l i

2.7 Quadrant Power Tilt Ratio - QPTR (Specification 3/4.2.4) j L

l L

The Quadrant Power Tilt Ratio (QPTR).shall not exceed 1.03.

l i

l 3.0. REACTOR CORE PROTECTIVE LIMITS I

(

'J 3.1 Trip Reset Term ( fs (AI) -)

for Overtemperature Delta i Trip (Specification 2.2.1) j s

j The following parameters are required to specify the power level-dependent f (AI) trip reset term limits for the Overtemperature Delta T 1

t J

trip function:

3.1.1 QTNL = -33%

i i

where QTNL =-the maximum negative AI setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.1.2 QTPL = +25%

where QTPL = the maximum positive AI setpoint at rated thermal Y

power at whi;h the trip setpoint is not reduced by i

i the axial power distribution.

3.1.3 QTNS = 2.80%

1 4

where QTNS = the percent reduction in Overtemperature Delta T trip setpoint for each percent that the nagnitude of AI t.

exceeds its negative limit at rated themal power (QTNL).

i I ' jSC)D i her/

Y, SEQUOYAH - UNIT 1 Page 6 of 12 Revision 0 4

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