ML20082M874

Illinois Power Co CPS COLR for Reload 5 Cycle 6, Rev 0

ML20082M874
Person / Time
Site:	Clinton
Issue date:	04/21/1995
From:	Shie-Jeng Peng, Rowe S ILLINOIS POWER CO.
To:
Shared Package
ML20082M839	List: ML20082M874 U-602438, Forwards Plant COLR for Reload 5/operating Cycle 6
References
NUDOCS 9504240409
Download: ML20082M874 (19)

Text

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' ILLINOIS POWER COMPANY i

I CLINTON POWER STATION j

CORE OPERATING LIMITS REPORT I

i FOR RELOAD 5 j

CYCLE 6 REVISION 0 7

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/6 l' AIL,h5 i

s S. I'. Rowe (Preparer)

Date NuclearFuel& Analysis i

4f$~ W f

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4

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t S. J. Peng (16fvid6er)

/

Date Nuclear Fuel Analysis H

I 4-to 'r f

~

FRd Date A

/ 4-Z0 46

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_w Manager-Clinton Power Station Date

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/ YW-95~

t-Director-LicerIsing Date

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M8455/269 9504240409 950421 PDR ADOCK 05000461

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INDEX l

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INTRODUCTION AND S UMMARY........................................................... 3 i

LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.1-AVERAGE........

4' l

PLANAR LINEAR HEAT GENERATION RATE (APLHGR) -

l

~,

LIMITS A61 CABLE TO TECHNICAL SPECIFICATION LCO 3.2.2-MINIMUM.......

12 CRITICAL POWER RATIO (MCPR)

LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.3-LINEAR HEAT. 16 i

GENERATION RATE (LHGR)

LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.3.1.1-REACTOR....... 1 PROTECTION SYSTEM (RPS) INSTRUMENTATION REFERENCES.........

............................................................18 i

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M8455/269 2

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f INTRODUCTION AND

SUMMARY

The CORE OPERATING LIMITS REPORT (Reference 1) is the Clinton-specific i

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 (MCPR ), the core thermal power-dependent.

f 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 cycle-specific core operating limits are determined for each reload cycle in accordance l

with Technical Specification 5.6.5. Per the Technical Specification, these values have i

been determined using NRC-approved methodology (References 2,3) and are established l

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.

t l

i M8455/269 '

3

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LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.1 I

POWER DISTRU}_UTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE All AVERAGE PLANAR LINEAR HEAT GENERATION 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 MAPLIIGR limits for each fuel bundle type and lattice are contained in Reference 4; the associated MAPLHGR multipliers can 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:

t

. 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 smalbst of MAPFACr, MAPFAC, or a factor of 0.78.

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FOR 4d% < P s 100% i ALL CORE FLON -

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20 40 60 80 100.

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e CORE THERMAL POWER (% rated), P l.

J Figure 2.1-2 Power-Dependent MAPLHGR Factors (MAPFACp) i I

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CLINTON UNIT 1 /*

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!. pe+t . n. h.v., . e. j, .6 w n. 4a, ,,un. m: 1. 4, 4 ... p -, p .,p<. -4 e, pp wH ,.s.w. H, ,.g p ..+ p h y....n. y .,n,.,.n m:, o ,i, .r m-. , ep p 4,.. o. g& n ...i. ..o 3w. m .w - .m ,m.,.t., 4 2 ..a 5 O 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) I Figure 2.1-7 Maximum Average Planar Linear Heat, Generation Rate (MAPLHGR) Versus Average Planar Exposure - Reload 5 Fuel Type - GE10-P8SXB348-10GZ-120M-150-T l l l CLINTON - UNIT 1 /e-wm .e

LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.2. POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO The MINIMUM 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 and 2.2-lb, and the MCPRp limits at indicated core flow and core THERMAL POWER and AT* as shown in Figure 2.2-2. These MCPR limits are consistent with Reference 5. s E D This AT refers to any reduction of rated feedwater temperature (420 F), such as prolonged removal of feedwater heater (s) from service with both reactor recirculation loops in operation. M8455/269 12

e 1.7 4 2. 5 s. . 2 . 2 . + 4. 4 4.....p.4 o 9 4 4.. 3 .4.. 1 .f.g 4 +. j..., 4. 4 .....7 , 7 ..:...,...i... ... q 7 , p, -.j :.4..i. ... j..i...! t. t..i., s. ...i... > m A q.- i.. j.4...p..,. 4 t. 4 p.+.. 9_, .u.. e ..3.. 1.6 ~.. , i .,4i ..,..i..,, i.~, 1 9 y ..g. .....l.. 4-.. i , FOR MAX RUNOUT FLOW GETTNG = 109.0%.... - - + MCPRf. =_ MA. X (1.24, 1.841-0.00707F) - t .[ v-e g -. 4 i, a E j 4 s > + 4 6 .a .,..q...,..q., ., s,,. ..p. ...j. ...h.-. l-.. S... p i ; o 4 1.5 , 4.+. .. g ......p.g....p y . y... e e i + > t s t .i.- 7 F-.*= p.-....g..+.i. ><t i + i # c 5 p.- <--t.-..-.a .v. 4 +i

• l 1

-i e + a 1 ... Q..i... V 4 s ^ 3 .g .. 4..a .i..s t - # t... t . p..i 3 4 k .. 1.4 v e ,. 4... ;...v......i.., i g ...i.... ...p........# g C s .g a 6 s 1.3 .4 . h.1 ( qi ( l .g.i. g 4 +- 6 4 4 1 -Y.-3 3 q .i.. 4, j. FOR MAX RUNOUT FLOW SETTNG = 102.5% f + ~ H Wi ' ~' MCPR g. - MAX (1.24,1.746-0.0065sF)

• 1 ' '

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10 t I t f J a, ........i, ..i.... 1.1 ~ d \\ w. 9 e f 4 4 i e L i = 1 +9 t 9, ,, + t t 4 6 -t-4 5 v ( ) 1 I l f L 6 t

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A 9 4 1.0 0 20 40 60 80 100 120 CORE FLOW (% RATED), F Figure 2.2-la CLINTON MCPR f VERSUS CORE FLOW, RELOAD FUEL TYPES OTHER THAN GE10 CLINTON - UNIT 1 /-/e-um+a i

I e 3 1 2.2 , 6 ... s. -... .a. 4 ,, 4- ? J... e ..3.- . i,.. ' h.4...-- k. 4 4 4-4 h ) 4 i e + 1 t g-4. d.. . 1 . - + -. h. 4..i. . j.... i.....i... ., + i '4 i' .' i . i .,. 4 4.. 1 4 ..7. 4 j.d,. 4.y..&.v..p.f. 4..i ...,....-4 .. g.... r . 4 7 ;. ;- ....4...p4 g3 , 6 4 2*0 _.. a. q., .p.. q....... ...,......e.. 4., 7.. ..+.9.. 4 .........7.....,..,,. p .a. -;... 4 ....p e .,4 4 p .,..y.. .p.,. F.- e..i.., i. 4.i. 4....1 ..e H. 4..a. [. 4 pq.y4

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p. yo.

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. 5. H-,-,_,,~. a vor rio,,4o% g.q, 7 ;..+ e. w ....McP,R, f.=.~(1,841,-0.0, 0707F,)m. (10+0.0032(40-F)) ?.

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44 .. -.4. ;. 4.4 9 .,... e ..l s .a. ,q. ... j.. g e g... ~m 7 1.6 ' ~ .K ,4.. 4. r, . -.7.m.;.7. 4, ..a.i.-....i. .,1 ....p.4 4... ..u. s..i..[..;,, ;. 4... i..p. 1. j.. ;.. r i e4 .. 4..3 4 -p 2. .. Maximum Runout Flow =100.0% . = +.... ...g -.4,. .q...,, , i.L for Flow s40% ..for Flow e40% MCPRg= x((L746-0.00659F) .. MCPRg = Max (124.1841-0 00707F);...;...;

4.,

10+0.0032(40-F)) i J 4+4 -4.- ~ ' ' + ~ 1.4 r ..j.. 7. ..j...,, i3 e 9

4. 4

..p. .1 s 2 , 3., .. 4.. t 4 .p... 4.. e .g, ..., + _ 9 ,~,,97 3 a uno' t Flow =10L5% l, ,;,, ~ l 4.., L......i.f ,,1 Mealmum u ~ y.9 4 , W...l..i... o.4.. 4 4.... + fof Flow e40% 4.- + ~4.. e.f i +1 e 1.2 MCPR,= MAX (124.1746-0.00669F) M- - F - - ii e-r t +e p ,..m ,_g. r,..n,., ;..;. +.. 4..... t ..... r.. , i.. 4.. ..p.,.

'.4 6

, it .i.. ..o 2 6 t , >.i. + 4+3 4 g.- 4.- i .t -i .p. .e .h..f..d. a ...t..,....,. t s 4 4 a b e & d . b. 1 ..I-. ..5 .....a hq I p ;..j.. .4. 4 i q p. s +y s, p. 9 .p... ....1 1.0 - ;.-+.. ..a 4. ~' i 0 20 40 60 80 100 120 s i CORE FLOW (% RATED), F Figure 2.2-1b CLINTON MCPRf VERSUS CORE FLOW, RELOAD FUEL TYPE GE10 1 1 1 CLINTON - UNIT 1 f f., ,f,.n,m.

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,~.4..p..j.., y..n.n ..e 4 7 y. ,.. L +.m.. > t. g4 g.a..v,.4 p. a 2*2- +.3.>-- THERMAL POWER 25% s Ps40%F W4-++t t .H. 3 -, 4 J' CORE HDW

• S0%

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tte n M.CPRp =,2.10 + 0.0033(40-P) t-

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..y., y ...E,.d.,.a. [..h ' h,.h..d..' .h..d...h 5...h.. h.p d..f.. pd 9.. E.,..,..d ..,k.(...... 4 .i..i. , 4. 4.i.. .4.a .r,- ,a m 4 e4.. .m a4 ...m ~..h. '.. d- ...h.. ...n 3 .....h, . t y n 4

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.eqq. .. +., 3.. w ' ~TIIERMAL POWER 25% 's' P s 40%" t

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/ CORE MAW s50% "MT T 4......'., " .'MCPRp = 1.85 + 0.0133(40-P)"a.".M..i '. ! 4 s, e.a..+.v..p,.#..,. t. +, m i s .,4. 4 ^ J ~ ?. f --p w' ' q - p.,.,- 4"i - p' 4 i p,0.,' ,t. e-j-4 epy J 6 e f ,..tr y e-6. 4

s..q-g o 4

, 7 .q.., j..p.q. q. ! 4 4 7 ,. 4., p.+. t.., ,a. ..s e. ..L J.J. i.i., i.4 -.1.5 a.. 4 mj., .( ..3 Os 4 .!.). l,. i 4..L. j 4..;..j. 4..? '..i.4.4..! 4 4..;. 4 .....p . } ' '. ; [.y ^, ; .y.,. ' j g - 9 . +. .a %.y n + ! q {. g .e p e 1 . p.; 7 7, _, .a-4 p4..p9 y p. p a 7 7.2. g..A.4.. j ..q.... _ g,7 ..9... 7..j..q. 7. 4.q..A.a...j , 7 ,.+ .y +. py...a s vn.4.p. H g ,q. ,, 79 4., 6.i. 4 4 f ;.4 4..i., .&.1.4.....i. 4. 4..+..;.. 4.+. i. 9..... p ;. e54 j.. i ..{.4 4..j. 4 ".q.., 44..i.4443 74 Q.', 4.a J. 4 4.. e 1*6 -.,m -,.4-

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'y. THERMAL POWER 40%

• P 5701 4 4 4 41.y. :

. a i. L. MCPRp =,.1.46 + 0.0045(70-P)

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.r. t. c t' , t -+- 8 +'.+t*1 I .'I t ..a. . +. ' - '., _ - L ( ) ..I $ i 9 h o, '*F. T-af .a. .y a.'.. .t. 4 ..q h 1g4 a i . 09 6 p i t 6 ,.4 +0 v.. { p., 4 1., f. e.* , o

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.e.t.. .t. . e.m -..,y f* a s, ? t"","t."T.-TW-,fr' 1 ,..g..J 8 1 5 r'** *...,... _. +.. ,. e. n..t .'*;,1, 4. "t'

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1 ' 5 ...j 4-- 6 fa A p'.y"t p c.4 + , 4.- .....m .a...u.4..; +a..>. ~ .. TIIERMAL POWER P > 70% w ' - NCPRp = MAX [1.24.1.21 + 0.0059(100-P)]" * * + + + - 1.2 ,.e.--,.,..,.... +. v..,e w...,..y. 4.. ,.,.4.. 4 .,,,em,.

....7+t.. ru..

+ .y4, 4,. 4 4.+..; 4.. ..t.. .p.i..y. i 1.{.4..j... 4 4..j.4 4.,.i,p.4 _ j.. 3 s4 4 ia. .. p.e.4 .+.. 4..i-.4 +4 4 a.. - 4, . 3 4 ' ~ -4 4.#.. .t 4 .f..~ j. ~.4.. l 1.1.j..p 4..[. j + 4,4, + s t-q ..} g a. (.4 g. 7 e 4 - 7 44. . <.. + +. <. .--e e. J; .. b 4.41.; j....14.. } 1.0 . [ 4 & i. 4, 4 . s. l.J j 4,.i & v.-p i 0 20 40 60 80 100 i i CORE THERMAL POWER (% rated), P l f 5 Figure 2.2-2 Clinton MCPR Versus Power for AT 550*F and Core Flow s107% p l CLINTON - UNIT 1 u =~ c y y

i i ' LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.3 EQWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE I The LINEAR HEAT GENERATION RATE (LHGR) for each fuel bundle type (References 6,7) shall not exceed the limits specified below; a. A maximum LHGR of 13.4 kW/R for the following fuel bundle type - BP8 SRB 299LA (BP8x8R) b. A maximum LIIGR of 14.4 kW/R for the following fuel bundle types - GE8B-P8SQB301-10GZ-120M-150-T GE10-P8SXB322-10GZ-120M-150-T GE10-P8SXB346-10GZ-120M-150-T GE10-P8SXB348-10GZ-120M-150-T i E l M8455/269 16 .l _ _____.____.____.___j

\\ y w LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.3.1.I SIMULATED THERMAL POWER TIME CONSTANT 1 i 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). l 1 I 4 [ M8455/269 17

REFERENCES ~ l. 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). 3. " Maximum Extended Operating Domain and Feedwater Heater Out-of-Service Analysis for Clinton Power Station," GE Report NEDC-31546P, August 1988. 4.A. " Supplemental Reload Licensing Submittal for Clinton Power Station Unit 1 Reload 2, Cycle 3," GE Document 23 A5976, Revision 0, July 1990. 4.B. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 3, Cycle 4," GE Document 23 A7144AA, Revision 0, Supplement 1, January 1992. 4.C. " Lattice-Dependent MAPLHGR Report for Clinton Power Station Unit 1 Reload 4, Cycle 5," GE Document 23 A7213 AA, Revision 0, October 1993. 4.D. " Lattice Dependent MAPLHGR Report for Clinton Power Station Unit 1 Reload 5, Cycle 6," GE Document DRF J11-02425 MAP, Revision 0, February 1995.

5. A.

" Supplemental Reload Licensing Submittal for Clinton Power Station Unit 1 Reload 2, Cycle 3," GE Document 23 A5976, Revision 0, July 1990. 5.B. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 3 Cycle 4," GE Document 23 A7144, Revision 0, January 1992. 5.C. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 4 Cycle 5," GE Document 23 A7213, Revision 0, October 1993. 5.D. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1, Reload 5 Cycle 6," GE Document DRF J11-02425SRLR, Revision 0, February 1995. 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. 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. M8455/269 18

-- i j 8. Letter to Nuclear Regubtory Commission from J. S. Perry (IP), "Clinton Power. Station Proposed Amendment of Facility Operating License No. NPF-62," 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 J. T. Worthington (GE), " Time Constant for Simulated Thermal Power Monitor," JTW:93-128, September 1,1993. I i 1 i i t i l M8455/269 19 .}}