ML20056C490

Rev 2 to Clinton Power Station Core Operating Limits Rept for Reload 3,Cycle 4

ML20056C490
Person / Time
Site:	Clinton
Issue date:	06/18/1993
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20056C487	List: ML20056C490 U-602148, Forwards Rev 2 to Clinton Power Station Core Operating Limits Rept for Reload 3,Cycle 4, Reflecting Incorporation of cycle-specific Parameter,Per Amend 75 to Plant OL, Permitting Removal of Parameter from TS
References
NUDOCS 9306240264
Download: ML20056C490 (18)

Text

..,. . .. .. .. . - - - - - - - - - - - - -

ILLINOIS POWER COMPANY CLINTON POWER STATION CORE OPERATING LIMITS REPORT FOR l'

RELOAD 3 CYCLE 4 REVISION 2

~

/

Lk & I hl Supervisor - Nuclear (NSND) ' Date FRG b #

S I b 7 l3

' Date IM '

44 --- / d {l b Dale MahTClinton Power Station

.( O id5AfiA /1 [ fA f AcD. / 6-M-93 Director - Licensing - Date '

9306240264 930618 $

l DR ADOCK 0500 1

1

, INDEX I NTR O D U CTI O N A N D S U M M A R Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 LIMITS APPLICABLE TO TECHNICAL SPECIFICATION 3/4.2.1-AVERAGE ........... 4-PLANAR LINEAR HEAT GENERATION RATE LIMITS APPLICABLE TO TECHNICAL SPECIFICATION 3/4.2.3-MINIMUM ..........12 CRITICAL POWER RATIO 1

LIMrFS APPLICABLE TO TECHNICAL SPECIFICATION 3/4.2.4-LINEAR HEAT ....16 - -F GENERATION RATE l

l LIMITS APPLICABLE TO TECHNICAL SPECIFICATIONS 2.2.1-REACTOR ...........17 PROTECTION SYSTEM INSTRUMENTATION SETPOINTS AND 3/4.3.1-RFACTOR PROTECTION SYSTEM INSTRUMENTATION

' R EF EREN C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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Revision 2'- .

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INTRODUCTION AND

SUMMARY

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The CORE OPERATING LIMITS REPORT is the Clinton-specific document  ;

that provides the values of the AVERAGE PLANAR LINEAR HEAT GENERATION RATE (AP1JtGR) limits, the core flow dependent MINIMUM CRITICAL POWER RATIO (MCPR) limits (MCPR f ), the thermal power dependent MCPR limits t

(MCPR p ), and the LINEAR IIEAT GENERATION RATE (LilGR) limits for the current operating reload cycle. These cycle-specific core operat.ing ,

limits are determined for each reload cycle in accordance with Technical Specification.6.9.1.9. Per the Technical Specification, these values have been determined using NRC - approved methodology 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.

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l LIMITS APPLICABLE TO TECHNICAL SPECIFICATION 3/4.2.1 i

POWER DISTRIBUTION LIMITS AVERAGC I'IHIAR LINFAR HFAT .CENERATION RATE All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APulGRs) for each l type of fuel as a function of axial location and AVERAGE PIANAR:

• EXPOSURE shall not exceed limits based on applicable HAPulGR limit '

values which have been approved for the particular fuel type and axial region (lattice). The MAPUlGR limits for each fuel type are contained in Reference 4.

When manual calculations are required, all APulGRs for each type of fuel 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 multiplied by the smaller of either the flow-dependent HAPu!GR factor (HAPFAC f ) of Figure 2.1-1 or the power-dependent MAPUlGR factor (HAPFAC p ) of-Figure 2.1-2.

b. During single recirculation loop operation - the limits-shown in Figures 2.1-3-through 2.1-7 multiplied by the smallest of MAPFAC f . HAPFACp or a factor of 0.78, t

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FOR MAX RUNOUT lLOW SETTING = 102.5%i MATEACf = MIN (10. 0 4800 + 0.006704F) \

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U 'FOR MAX RUNOUT FLOW SETTING = 109.0%"* - .

< MAPFAct a MIN (1.0, 0.4430 + 0.00G770F)?  ;

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- Figure 2.1 -1 Flow-Dependent MAPLHGR Factors- (MAPFACf )  ;

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FOR 40% < P s 100% : All CORE FL0WS P FOR 25% s P e 40% : CCHE FLOW F s 50%

g / MAPFACp = 1.0 + 0.0052 (P - 100).

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FOR 25% s " P s'40%': CORE FLOW F's 50%

MAPFACp = 0.6 + 0.002 (P - 4 0)

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0.5 1 0.4 - ~

0 20 40 00 80 100 120 L CORE THERMAL POWER (% rated), P 1'

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Figure 2.1-2 Power-Dependent MAPLIIGR Factors . (MAPFACp).

1 i- CLINTON - UNIT 1-  : ,

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L Figure 2.1-4 Maximum Average Planar Linear lleat Generation' Rate ,

(MAPLIIGR) Versus Averane Planar Exposure -

Reload 1 Fuel Type BP8fRB284L i CLINTON - UNIT 1 ,

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12.6 12.6 - 12 6 12.6 3

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AVERAGE PLANAR EXPOSURE (mwd /ST)  !

Figure 2.1-5 Maximum Average Planar Linear IIcal Generation ' Rate (MAPLilGR) Versus Average Planar Exposure - l Reload 1 Fuel Type BP8 SRB 284LC CLINTON - UNIT 1 i y

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I-i AVERAGE PLANAR EXPOSURE (mwd /ST)

Figure 2.1 -0 Maximum Average Planar Linear IIeat Generation Rate l

(MAPLIIGR) Versus Average Planar Exposure -

Reload 2 Fuel Type BPBSRB299LA .

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0 5.000 10,000 .15,000 20,000 25,000 30,000 35,000 40.000 45,000 50,000 AVERAGE PLANAR EXPOSURE _(mwd /ST)

Figure 2.1-7 Maximum Average Planar Linear Heat Generation' Rate MAPLIIGR) Versus Average Planar Exposure, teload 3- Fuel Type - GE8B-P8SQB301-10GZ-120M-150-T ~

CLINTON - UNIT 1 .

= - . .

4

.d LIMITS APPLICABLE TO TECHNICAL SPECIFICATION 3/4.2.3 POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than both the MCPRf limits ar indicated core flow and TIIERMAL POWER for each fuel type as shown in Figures 2.2-la and 2.2-lb and the as MCPR p limits at indicated core flow and TilERMAL POWER and A T shown in Figure 2.2-2.

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• This AT refers to any reduction of rated feedwater temperature l

l (420*F), such as prolonged removal of feedwater heater (s) from service with both reactor recirculation loops in operation.

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r I

l CLINTON - UNIT 1 REVISION 1

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FOR MAX RUNOUT FLOW SETTING = 109.0%.-

MCPR ...f..=..u... MAX (.120,1841..0.00707F) a.m 7

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.. .1 A A A 1 d., 11' O 20 40 60 80 100 120 CORE FLOW (chRATED), F Figure 2.2-l b CLINTON MCPR p VERSUS CORE FLOW, RELOAD 3 FUEL TYPE GE8B-P8SQB301 - 10GZ- 120M- 150-T CLINTON - UNIT 1 REVISION 1

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

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TilERMAL POWER 25% 1 Ps 40% -

CORE FLOW > S0%

MCPHp = 2.10 + 0.0033(40-P) -; .. , ,

- + v

~

2.0 ---

WER 25% s P s 40%

/.TIIERMAL CORE FLOW PCs 50%

MCPRp = 1.85 + 0.0133(40-P) i 1.0 g < ..,

s . .,

-iJ i 1.0- .

TilERMAL POWER"40% iP s70% - . .'

MCPRp = 1.43.+ 0.0045(70-P) ' - .

t I I

• f *T I I.4 , , ,

. . .... . . . . , ['

. .TIIERMAt., POWER P = 70%. . -

..i '

? MCPRp = 1.18 + 0.0059(100-P) .. . . -i 1.2 , 3 , ,

, 4

- 4 9  ;- -

• 7 r i i

L I-P t

' }-

i ,

1.0 O 20 40 60 80 100 120 CORE TIIERMAL POWER (% rated); P

' Figure 2.2-2 Clinton MCPRpVersus Power for AT s50 F and Core Flow s107%

I CLINTON= - UNIT 1 -  :-i

.- ~.

P d

'i LIMITS APPLICABLE TO TECllNICAL SPECIFICATION 3/4.2.4 i POWER DISTRIBUTION LTMITS LINEAR HEAT CENERATION RATE The LINEAR HEAT CENERATION RATE (UlGR) for each type of fuel shall not exceed the limits specified below;

a. A maximum IJIGR of 13.4 kW/ft for the following fuel types - ,

P8 SRB 200 .

BP8 SRB 284L i BP8 SRB 284LC BP8 SRB 299LA i

b. A maximum UlGR of 14.4 kW/f t for the following fuel type -

CE8B-P8SQB301-10GZ-120M-150-T ,

l l.

I

?

l -~'

l

- .L..

s F

~

11 hilts A~PPLICABLE TO TECHNICAL SPECIFICATIONS 2.2.1 AND 3/4.3.1 5IMULATED THERMAL POWER TIME CONSTANT 1he Average Power Range Monitor (APRM) simulated thermal power time constant s: tall be between 5.4 seconds and 6.6 seconds.

i Revision 2

EEFERENCES

1. CPS Technical Specification 6.9.1.9, CORE OPERATING LIMITS REPORT.

I 2, General Electric Standard Application for Reactor Fuel (GESTAR), NEDE-240  !

Il-P-A, as amended (latest approved version). l

3. Maximum Extended Operating Domain and Feedwater Heater Out-of-Service Analysis for Clinton Power Station, NEDC-31546P, August 1988.

4.A. CPS Updated Safety Analysis Report, Table 6.3-6, "MAPLHGR, MAXIMUM LOCAL OXIDATION, AND PEAK CLADDING TEMPERATURE VERSUS EXPOSURE.

• 4.B Document 23A5921, Revision 0, " Supplemental Reload Licensing Submittal for Clinton Power Station Unit 1 Reload 1, Cycle 2," August 1988.

1 4.C. Document 23A5976, Revision 0, " Supplemental Reload Licensing Submittal for Clinton Power Station Unit 1 Reload 2, Cycle 3," July 1990.

4. D. Document 23A7144AA, Revision 0, Supplement 1, " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 3, Cycle 4, " January 1992.

5. Letter JTW: 92-085, J. T. Worthington (GE) to J. A. Miller (IP), "Clinton Cycle 4 Rotated Bundle Analysis," May 19, 1992.

6. Letter JSP: U-602085, J. S. Perry (IP) to Nuclear Regulatory Commission, .

"Clinton Power Station Proposed Amendment of Facility Operating License No. '

NPF-62" [LS-92-004], February 11,1993.

7. Letter DVP: D. V. Pickett (NRC) to F. A. Spangenberg (IP), " Issuance of l Amendment [75] (TAC NO. M85816)," May 25,1993.

.l Revision 2 1 1:

l'