ML20137C580

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Rev 0 to CPS COLR for Reload 6 Cycle 7
ML20137C580
Person / Time
Site: Clinton Constellation icon.png
Issue date: 03/20/1997
From: Shie-Jeng Peng, Rowe S
ILLINOIS POWER CO.
To:
Shared Package
ML20137C579 List:
References
NUDOCS 9703250048
Download: ML20137C580 (22)
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Text

{{#Wiki_filter:. 4 ILLINOIS POWER COMPANY CLINTON POWER STATION CORE OPERATING LIMITS REPORT j i FOR RELOAD 6 i CYCLE 7 i REVISION 0 l I IL B l$97 S. L. Rowe (Preparer) Date Nuclear Fuel & Analysis t ~ I 2-U~il S. J. Peng (ReWewerf / Date Nuclear Fuel & Analysis ) ~ /

2-1P-17 M/

FRG Date j / Ab/k? Manager-dlinton Pg(vefr' Station ~/ Date b. & T.J.Tet4Lw d / 3/20/S7 i Director-Licensing Date 9703250048 970320 PDR ADOCK 05000461 p PDR M9119/293

INDEX INTRODUCTION AND

SUMMARY

3 LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 5.2.1-AVERAGE. 4 PLANAR LINEAR HEAT GENERATION RATE (APLllGR) LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.2-MINIMUM. 12 CRITICAL POWER RATIO (MCPR) LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.3-LINEAR HEAT. 19 GENERATION. RATE (LHGR) LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.3.1.1-SIMULATED.. 20 THERMAL POWER TIME CONSTANT REFERENCES........ 21 hi8455/269 2

i .i 5 l 1 l i i i INTRODUCTION AND

SUMMARY

I ~ The CORE OPERATING LIMITS REPORT (Reference 1)is the Clinton-specific l document that provides the values of the AVERAGE PLANAR LINEAR HEAT ) GENERATION RATE (APLHGR) limits, the core flow-dependent MINIMUM - CRITICAL POWER RATIO (MCPR) limits (MCPRr), the core thermal power-dependent l MCPR limits (MCPR ), the LINEAR HEAT GENERATION RATE (LHGR) limits, and p the simulated thermal power time constant for the current operating reload cycle. These I cycle-specific core operating limits are determined for each reload cycle in accordance with Technical Specification 5.6.5. Per the Technical Specification, these values have been determined using NRC-approved methodology (References 2,3) and are established such that all applicable limits of the plant safety analysis are met. Plant operation within these operating limits is addressed in the applicable Technical Specifications. I i i I L i N18455/269 3 l l

i . LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.1 l P_0_WER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE [ All AVERAGE PLANAR LINEAR HEAT GENERAT ON RATES (APLHGR's) for each type of fuel as a function of axial location and average planar exposure shall not exceed limits based on applicable MAPLHGR limit values which have been approved for the particular fuel bundle type and bundle axial region (lattice). The MAPLHGR limits for each fuel bundle type and lattice are contained in Reference 4; the associated MAPLHGR multipliers c'an be found in Figures 2.1-1 and 2.1-2 which are consistent with Reference 3. When manual calculations are required, all APLHGR's for each fuel bundle type as a function of average planar exposure shall not exceed the limits as determined below: a. During two-recirculation loop operation - the limits shown in Figures 2.1-3 through 2.1-7 (Reference 5) multiplied by the smaller of either the core flow-dependent MAPLHGR factor (MAPFACr) of Figure 2.1-1, or the core thermal power dependent MAPLHGR factor (MAPFAC ) of Figure 2.1-2. p b. During single recirculation loop operation - the limits shown in Figures 2.1-3 through 2.1-7 multiplied by the smallest of MAPFACr, MAPFAC, or a factor of 0.78 (Reference 5). p \\ l l l M9119/293 4

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,m m, n, 9 0,.,, - p., ;...,., .-_..; ;j. .. m,,, a. o..- +,- .m. , s.e,+,,.1 ,m m n., a m ms e, ,3n,, 4 g, m.. n .m, +, u ,,m +,,,...o .. m , e e d.r, m we, a >H4+ 91: ,n tea. >4 i-. n,

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ai a a., +r = u.n,, . nt, m - 4. a4. m ; w1 ,;i. e, 'm .i m., . 4 -;.;., a ..u - ,w s so, 4 m., m c ;; ime o,, m, ~, m, a . i - . ~ u, 5 0 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 50,000 55,000 AVERAGE PLANAR EXPOSURE (mwd ST) Figure 2.1-0 Maximum Avera ge Planar Linear Heat Generation Rate (MAPLHGR) Limi; Versus Average Planar Exposure - Reload 5 Fuel Type - GE10-P8SXB348-10GZ-'120M-150-T CLINTON - UNIT 1 /=./.r.4..eri,/eeries.i-e

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3.,,m,,

6.e t o ,,.s e. i. , e ,s,, m,--, m m -,. m.m p pi - 4i 4 < q p. 3.jd.4 m+ ,,,+e yp+ es 6 iy.i tj,.(t e y.e,et, t 4 a a > si o 4 i ..o i ... i r ..a r4q i .a i e - i 6. m !. m .i m % i pe .,-qt y, e.. > . i< +. <74 2 ++,,e,3 m-en,,_, t. w.- , r,., p.-.-, ,e~, ~. w+ i - 4 5 j. 0 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 50,000 55,000 l i AVERAGE PLANAR EXPOSURE (mwd ST) t l i t Figure 2.1-7 Maximum Averag' e Planar Linear IIcat Generation Rate (MAPLHGR) Limit Versus Average Planar Exposure - Reload 6 Fuel Type - GE10-P8SXB353-12GZ-120T-150-T 4 CLINTON - UNIT 1 /-/m w amo.i-v {' I, I

LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.2 POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO The MI'NIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than both the MCPRrlimits at indicated core flow and core THERMAL POWER for each fuel bundle type as shown in Figures 2.2-la through 2.2-Ic, and the MCPRp limits at indicated core flow and core THERMAL POWER and AT* as shown in Figures 2.2-2a through 2.2-2c. These MCPR limits are consistent with Reference 5. l l i This AT refers to any reduction of rated feedwater temperature (420 F), such as prolonped removal of feedwater heater (s) from service with both reactor recirculation loops in operation. M8455/269 12

~_. J 1 l'. 7 h,q a, 4 .. i 4.. 4 ... <. i. < 4 r i s i, 6 . + y 7..- ~ s. 4..p p. s ..~ .4 i 4 4-. + <

i.. e 7

i .. i., e a c ,a a-e.~ t ( g 9\\* f s 4 f 9 Y S 1.6 3 j 6 4. i ,. 1 s i e 4 c p.. i (UNOUT FLOW = 109.0%--...... j . FOR MAXIMUM ...p, 4 l _'.'.... i - MCPRg = MAX 124,1.875411-0.007202F][ 4 9 I 4-4.- 4 ( 4 6-L 6 F T 8 = b...). j i,.. .. <, 4 o, --4 ~ .r q,-., 1.5 ..p., + 1 ..,.i, ,..<4... ..m.. a e +, <,> n, e + * ~ l , e , 4 4, 4 ..e., 4 -,,., e i e e. .. 4 +1,... t I i,,,.,. 1.4 ( f f 8-t d i,,, 4 I E 3 I= .\\ 7.N 4- ,, 7 < g j..- . i e i, i i e. e- ,, i 4, i s ..~ - -. - O i O 4 y ..H.., 1.3 ,. -. e.. ...,p.. e- , i - j e. + - y, e 77~ e + ~i '," FOR MAXIMUM RUNOUT FLOW k 102.5%f =. MAX [1.24,1.778636-0.006713FP H 'r l MCPR I d b e ? t t c 4 1 1.2 ..e 9.,f.... 4. 9 9 3 ,,m...., -.+.., 2.. t e . i. g 1.1 2 4 u i 2. .+ 4 ,.y..s - f. g..a f. =- f i g t 1 1 t 5 t t 1.0 t-9 e. a t t , t 0 20 40-60 80 100 120 CORE FLOW (% RATED), F Figure 2.2-1 a Flow-Dependent MCPR Limits, Reload Fuel Type GE8B CLINTON - UNIT 1 /- / 7.--w=.u-i.

~. '4 l 1 1 . u a t .. TI - y e g B..F -. q - .P ,. c.f 3 P 5. ~, e 1 w 6 J 4 ) 4 .a 4 r y., ..j.. 3 4 +. 2.0 4 ,i4 Jh. ~ ~~....p.I CORE FLOW s40% ~ " i ~....b i MCPR = (1.875411-0.007202F)r(1.0+0.0032(40-F)).j.. m-. +. 7 7 . q.. .,g..,. i ~., ..1.. j p F r= (-' .-d-t ,f ) .J b ..p- . r --, .m. 4 1.8

e a m -.

4 .2... ,4 g 4. ..y s , +... C.) u ,..i.. ..p. y g -.c., p -,.,. i .2..- ~ 1.6 , o 7...,. .. a ,, ~ s. 3 ^ ^ 3 ~ 1 ^ ". l pdR' M Xkh Und $NNOUT Fk.0W'=109.U% .t.. CORE FLOW 540% ~ ~. MCPR = (1778636-0.00671x 1.0+0.0032(40-F) )- Q...,. RE FIDW E4 % g .MCPRg= MAX .26,1.875411-0.007202F]. 7,' .h, t a- =, ~ + t I ( ,.j. 7 .r...-_,.a. lF'OR M'AXI'MU RUNU T FLOWhiO2!5'1' " l ~ ~ Q... i

- +... CORE FLOWE40%

"McPR : MAX [1.26,1.778636-0.006713F1-12 f, l t .,~ ~. i , ~., - y.p. i. 7.. 4 i j q. ,..i. i i.- 3 a.- l 0 20 40 60 80 100 120 CORE FLOW (% RATED), F Figure 2.2-Ib Flow-Dependent MCPR Limits, Reload Fuel Type GE10 with Bundle Averaged Exposure Less Than or Equal to 2000 mwd /ST l CLINTON - UNIT 1 f, f.,,,,. _,,,,,,,,.,_,, l l I

. 4 i 2.2 H 7 4 .g j _.... +...... ...p.. ..p i a- , + i,+, , s. i [ t 1 4 + 3 , t i i . -j 4 4 ij,,,,,. { . -.. 1 2.0 ~ ~ 5',. a.;. MCPR = (1.875411-0.007202F)x(1.0+0.0032(40-F)); '.T.: f CORE FLOW s40%' ,+ g... 1 4 --+,. i... 4 e,, -e.,....., . 1 ,er, ,+.., . 4, 9 5 s 1.8 7 -...3,.. c

e. 3 9..,.,

m , s., ,t g . t.,, g ....<.7.. .,.-m ..a g -t <1 i 3 . p. s.4... .4 1.6 / r.-., / i 4 4- -h 4e f.- -f. 4 3 = ...' ~4! i FOR' MAXIMUM RUNOUT FLOW =109.0% ~ CORE FLOWS 40% / MCPR = (1.778636-0.036713F) k, CORE FIDWe40%MCPRg= MAX [1.24,1.875411- 0 0 g x(1.0+0.0032(40-F)) ,. r. .y.. i.;% ...g I 4 > ms ) v r 2 i c .. FOR MA.GMU RUNOUT FLOWh$02 5%"' ~ ' ~ 4 CORE FLOWe401 - r - i '~ MCPR = MAX [1.24.1.778636-0.006713FU l t j,g g js. t..;.. 1 e ,. 1. ~ e.~.. i i ..u m,_.-,, 2 c.+ A d A 9 4-j - *.. 4 4 4.. e op e. ..r.. 4,, 4 +,,, .... ~. 1.0 O 20 40 60 80 100 120 CORE FLOW (% RATED), F Figure 2.2-ic Flow-Dependent MCPR Limits, Reload Fuel Type GE10 with Bundle Averaged Exposure Greater Than 2000 mwd /ST CLINTON - UNIT 1 f../.,.._wm,u..

l l \\ l. I t I i i 2.4 e,,, . p. .... q. p,m. 4 ..j..,. _.9... 4 a,, t. + i, 3, y.. 2 ..p .4~ . j.., m23 i 1 ..i..... -}.. ; 4 y e a -4.., .. s.,,,, . z .L. .,.4 3.... 4 2*2 - TIIERMAL POWER 251 s P s 40% F + a-J 1 i " CORB FLOW $ 50% t ~ + - - ' MCPRp = 2.10 + 0.0033(40-P) r +' , 7.,.. p . ~. - - '~ .. q... I g 4 4 y 4.. (- w+ g ..y....

s....

g p.. .g..y.. ...y..{.. s.. t.. o & 6 6 c.J..., e. e... .9...y a -4 g. p g 3 J. 4 I ...p. .4....

1. ;

e. .... 6 , e q, g.. 4...; .....p.+.-- oa.....g. , 4. . 4 4.r -.. yTilERMAL POWER 25% 5 Ps 40%. - +- .t 2.0 CORE FLOWS 50% .jMCPRp = 1.85 + 0.0133(40-P)" ~ 4.... .H

e. 4 4

,....j...,. [ ...i...,..,. t. ..h...i... .L.-. ,...p.',d...........,;...,,-...,........,,..,,.. ...i...,..,... ,.,... + , _ TIIERMAL POWER 40%

  • P 550%; +.

. H. 4., 4 4 O 1 ,n MCPRp =.1.814 .m ...d.... g.+ e 7 .7.. J 4 s j.. 8. s g g..k ..p 4. k.. i a -).- y i- - 9

v..

4.. y. s.. p..., L. 4. g._ y

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  • P,60 P)"' '

, +..,....... ..+4 560%. ' ~ ; ^ N'?Mi M ' ". MCPR p = 1.737 + 0.00771 .'..y~.. i N. "._7 ' ' P ' ' ~ g .4 ..t.. .. _....... ca._ r g i....4 6 ...,..h -. 4 6. 6 + s,..a.. M l "' " H- ' ? !TIIE'RMAL POWE'R 60'%

  • P 57d% I

..d i ~-1 ' ' rr 1~ ' P 1. MCPR p = 1.605 + 0.0132(70-P) r. 1.6 ~ ,.. '., 4,,, ) e. 4. 7 q,- -3.t 7 i .r. ..a . +., --g 9 + p,. _.. L.e..p ...i.,..,... e.. .<....o . THERMAL POWER 70%

  • P 580% s-

...w ,,,g......h.

a. MCPR p = 1.407 + 0.0198(80-P).

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.. 2. X 4.., t.;... -.. ~......................... .2. 2..-. +- 'p 4 2.. - THERMAL POWER P > 80% " MCPRp = MAX [1.24,.t.M + 0.0059(100-P)] - + 5 1.2 <.....i w p -p... r H. i ., s... 4 ... j - i. i 4. + ,4 1 l ..!... 4.

i..

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'-4 4 ) i.. j... 4..p. s - ....j. p, - _ ;7.. _ _ 4,.. $ <, t i e.. i. , ^, -, o 1.0 0 20 40 60 80 100 CORE THERMAL POWER (% RATED), P Figure 2.2-2a Power-Dependent MCPR Limits, AT 550 F and Core Flow 5107%, Reload Fuel Type GE8B CLINTON - UNIT 1 <-e--u--

.4 9 t 2.4 .3 .,.,.1.. + +-; .. i....... s 4..+ .4{..., 7 , p -e p p q r 4 v t f 4. i.,. 1,, q. 1 4... 4. ,.,,i,>> +-i - THERMAL POWER 25% s P s 40%" -+ , 4 v i

c-CORE FLOW > 50%

.,! ". 9... g,.,, g e. 2. -.... _, .. 3. ~ MCPR. p = 2.10 + 0.0033(40-P)1, g. a .p. .q.. ., -p.

4. i.

. 4 4.. ,4 y. < .,.,. 7. y 4.. + .........4...m. 4.., 4.. 7..; a.. ", ,.7.. 2.0 pTHERMAL POWER 25% s Ps 40%. ., - + + CORE FLOW s 50% 'iMCPRp= 1.85 + 0.0133(40-P)"

  • b p.+...,,,.4

't ' e <. i 7 .- f l. ?... o-F-..... e e > ,-,t, +. +..,,., 4 4 .t .+t*'.>4-

4...,

...em.. .t, . i .;4, i.+ 4.. 4,.. 4' THERMAL POWER 40%

  • P s 50%.. +-

1. J.. b H. 7... . MCPRp = _.1.814 ... i .3. o ,. t .+.,

o. p.,

,,.. g.g 4.,. .,- 4. g ...i... ..2 4 gg ' " THERMAL POWER 50%

  • P s00%

~ 9,: ; MCPRp = 1.737 + 0.0077f 60-P)7. ..,.4 . g.. +... O 3 p. ...a....p. i t -a a 4. i.... - ..i b s-M 4 h THERMAL POWER 60'%'

  • P 570% '

' ' + 4 -

  • i MCPR p = 1.605 + 0.0132.(70-P).P

..e 2. ~ 4 l l.' ' ;.l I. dHERMAL POWEli 7 fVP E80% L. t.. + -.L - ; MCPR p = 1.407 + 0.019B(80-P)-,i + 7 7 ...) .J 4. + g h ...h..,... ... d. a 1. 4 =.- 4. ..g.. .h.. .4.. ,...... e 1.4 ...+ ..,-..r 4 . r c..,... 4. e. 4.... 4 .4 ., 4,, 4., 4...g ... g p.,, ; . q.- ,q.,, ..g....g....p..,, ...r, e v.,

q..

.;. 2... .q... 7 4 ..p....-9 ...._.4..=...,.--.......... ...y... -THERMAL POWER P > 80% a e MCPRp = MAX [1.26,1.22 + 0.0059(100-P)]- * > vr 1.2 ..,. f. a

v. j a

. e e .. ~. .p..> a ; . + i, + z. 3.- s 1 m i.4... , a... 4 . b.f v.h ..d... O i 6 4 e 4-3 4. 8 b 4 . 9 i t J g 1 .i... r.!~ 4 <

m. i.. i >

..i. '..,,5 '...i..j..., - i.. ...,4 e-a >. ...i. ....i 1.0 ~ ...L., 2 4, c ..>.a 0 20 40 60 80 100 CORE THERMAL POWER (% RATED), P I l I Figure 2.2-2b Power-Dependent MCPR Limits, AT s50 F and Core Flow s107%, j Reload Fuel Type GE10 with Bundle Averag/ST ed Exposure Less Than or Equal to 2000 mwd CLJNTON - UNIT 1 - s- - i l i (

e 9 e o e 4 4 2.4 w.y. m .,...p. 4 4*

  • . -i o t 4.j u 4

4 &. a ... q..J,. 4.... +. e.z,...p p.q... s 4

c. i...i s,.. l i

e u o 4 ..n., ., e,

... 4.,...;-

3 4 4 ..e....

i. ~

.. 4.., . i..d ..i. 2. ..j.. q. .( 4 ,...p.., ...p.., 4, , i 1... t t. ;, ...L... ..j.. ..p..;.....i. 4.. j.. .4.. e... . !...i...,,,.;...,i 7 4. i..+ ' '

4...]...

4.i 1..; 4 4. La ..A.t i i : i4, o.j. ...i.... i .. 4 L.s.., ..,j... ..q... &. 4 e,,, e d. . 4.,, .. +. 4...q .. i. - +e 4 4.. i 4 7. ,t 4 7.,,,, .4 ,. 4... q...,.. t ,. 4..a q-..a. 4 4 +. t.1.. p.., t.# : i ,,, 4 2a2 y.1, . THERMAL POWER 25% s Ps40%i ~m. t ,...a..+.; ....+y.+ CORE FIDW > 50% i 7 ..; 4. - m..m.. " MCPR. p = 2.10 + 0.0033(40-P)"; +~ 4 ......, m ..,. - y a... s .; :.4.._g

.g...,. p
s. u,.

>7 ...p.. 7 3. .,y...,.,. 9 i ...i. .. s ,.a..4.. .A. ..7.. .p.e. ..q. i.3. 4 a.4.i...j ..i ...... -.-4.....,a ..g,., ,.7 ..o. 2.0 ~ g.g.4 - c pTHERMAL POWER 25% s Ps 40%. -+ _,,a n 4 cor. Flow s 50% E.P.* MCPRp.= 1.85 + 0.0133(40 P) ' ' F- .g..... ... p., q.. . 4.a ,3.., 73 .r,,

e. 6. 6.+

e p +, ., - 4

u. & s -

.,n-.L..> ,.,.....v..i..,, -4..., . i. i. ..4....i.. l. 4..., c. i-..,. 4m ;. ...m 5s...*.+......L.....m, e L L..;...:.i..... 1. 1 4..., 2 THERMAL POWER 40%

  • P s50%!.4
q..j. _,

t..;.... MCPRp =..1.814

3..
i r.

...g.. .g # ...p.. y.4

4. 4..
q., q...:.p.

.-<,.i..-, 94 4

a.. a e
4..-

.. 5.. } .. i...,,..s...<m.4. a 5 o .d.... u..i

i. 4,..

4 --i..q... ..}...#

4..

..,4.., 1.8 g . ;. ; 4........ ...r.g _ r., 3 ~~PTHERMAL POWER 50%

  • P 580%

~ "rF + ~" 1 MCPR p = 1.737 + 0.0077f 60-P)[ ~ ^ " A ...,1.., ~.... c O .a.d. 4. 4.. # oJ. + i. ... L a. ..-a ~L' 2 i 5 ; ' * - H THERMAL POWE'R' 60'% E P 57 15 # 'i lt**.....i,.'.1. MCPR p = 1.605 + 0.0132(70-P) r.

  • 1,,",'..

~ ' ' ' 1.6 ..p. ..d..4 ..1. 9 p.., u. i... i... -p.... ..... j. 4 = ..i..h l. [p........ 4 u ..L. e ,.5 4 4 4 L. (.1.. . 4. ,4.4.. - s.... .-s..<-.. e .i.. e e,, 4 a . p 4 ,... J -,.. T... .1.n THERMAL POWER 70%

  • P 580% m 44-,

~ MCPR p = 1.407 + 0.0198(80-P) & 4. ..i.4 4.< -t. ...q. 1... ......,.7 ..n.. .t _.u.. p g a.-.y., 6...,., ... +...,, ...+. .+.a... .u.+...p. 1.4 4 i~ a...... ;, .. p. i 4 ., 4 4.- >., +...

o. L., 4 e,.i -

i e. a,

2. ?..y. e t

, 4 + e : t...b e4 t i 3 4 4 .,,,,,s 1 . h p.4_-- gi.,..; e 4-- . 4 .'-h-,6 +t .....;.-?.-. t t A ..? , a. ,...i.. '.4_,,, , t. . 4.4 i .4 i.- -, r 7... I L ._.._. a ...i.......i... t 44_i.J L 4 . THERMAL POWER P > 80% ~ ~ .44.. q.g... ... +. - MCPRp = MAX [1.24,1,22 + 0.0050(100-P)]- 1.2 u, ~ .. 2..... ....e .4. i.y..i j. ..k ,. a. 7.. 7.,.. p,- ,.j...s... w - r...

4...s

.. q.. j.. j.., ' ' ' <..[. j.. . q. p.4..,- q

j. 4

.e 2 .. i 9 4.. p.4... .2... ...i.. _im . i , e .u a .l.. ........ m .. 3 ~i...l ... d. 4 4 -e . 4 ~.. _. ...,7

y.. q....

......q. ..~..a 4 .q.. ...-g., 4 _.-..a.... e.+ .4.. ..r.. , e.s 1.0 N.- h..' .d..... '...i...e. 4...h. 6 '.. h. - h.4 'p-4 --( ......h.4 ~ ' 5 p,.4..' - - - 2 L (. u i ',.h ~ 0 20 40 60 80 100 CORE THERMAL POWER (% RATED), P Figure 2.2-2c Power-Dependent MCPR Limits, AT 550*F and Core Flow 5107%, Reload Fuel Type GE10 wit,h Bundle Averaged Exposure Greater Than 2000 mwd /ST CLINTON - UNIT 1 -

I .? l l LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.3 POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATlQN RATE The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit of 14.4 kW/ft for the following fuel bundle types (References 6, 7): GE8B-P8SQB301-10GZ-120M-150-T l GE10-P8SXB322-10GZ-120M-150-T l GE10-P8SXB346-10GZ-120M-150-T GE10-P8SXB348-10GZ-120M-150-T GE10-P8SXB353-12GZ-120T-150-T l l M8455/269 19

b 4 4 t l LINilTS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.3.1.1 REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION SIMULATED THERMAL POWER TIME CONSTANT l 1 l The Average Power Range Monitor (APRM) simulated thermal power time constant (References 8,9) shall be between 5.4 seconds and 6.6 seconds (Reference 10). 1 i. i u ( l ) .I I I l \\ i l. I i l f 3 i M9119/293 20

'.4 e REFERENCES ) 1. CPS Technical Specification 5.6.5, CORE OPERATING LIMITS REPORT (COLR). 2. " General Electric Standard Application for Reactor Fuel" (GESTAR II), GE Licensing Topical Report.NEDE-24011-P-A, as amended (latest approved version). l 3. " Maximum Extended Operating Domain and Feedwater Heater Out-of-Service i Analysis for Clinton Power Station," GE Report NEDC-31546P, August 1988. 1

4. A.

" Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 3, Cycle 4," GE Document 23A7144AA, Revision 0, Supplement 1, January 1992. l 4.B. " Lattice-Dependent MAPLHGR Report for Clinton Power Station Unit 1 Reload 4, Cycle 5," GE Document 23A7213AA, Revision 0, October 1993. j 4.C. " Lattice Dependent MAPLHGR Report for Clinton Power Station Unit 1 Reload 5, Cycle 6," GE Document DRF J11-02425 MAP, Revision 0, February 1995. 4.D. " Lattice Dependent MAPLHGR Report for Clinton Power Station Unit 1 Reload 6, Cycle 7," GE Document DRF J11-02920 MAP, Revision 0, September 1996.

5. A.

" Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 3 Cycle 4," GE Document 23 A7144, Revision 0, January 1992. 5.B. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 4 Cycle 5 " GE Document 23 A7213, Revision 0, October 1993. 5.C. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 5 Cycle 6," GE Document DRF J11-02425SRLR, Revision 0, February 1995. 5.D. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 6 Cycle 7," GE Document DRF J11-02920SRLR, Revision 1, December 1996. 6. Letter to J. S. Charnley (GE) from C. O. Thomas (NRC), " Acceptance for Referencing of Licensing Topical Report NEDE-24011-P-A-6, Amendment 10, ' General Electric Standard Application for Reactor Fuel'," MFN-082-85, May 28, 1985. h19119/293 21

',4 7. Letter to J. S. Charnley (GE) from A. C. Thadani (NRC), " Acceptance for Referencing of Amendment 18 to General Electric Licensing Topical Report NEDE-24011-P-1,' General Electric Standard Application for Reactor Fuel'," May 12,1988. 8. Letter to Nuclear Regulatory Commission from J. S. Perry (IP), "Clinton Power Station Proposed Amendment of Facility Operating License No. NPF-62," i U-602085 [LS-92-004], February 11,1993. 9. Letter to F. A. Spangenberg (IP) from D.V. Pickett (NRC), " Issuance of Amendment [No. 75] (TAC No. M85816)," May 25,1993. 10. Letter to J. A. Miller (IP) from R. D. Williams (GE), " Simulated Thermal Power Monitor," RDW:95-160, November 16,1995. j i 1 ~ i i l d i M9119/293 22}}

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