ML20207F203
| ML20207F203 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/10/1999 |
| From: | Byam T, Hunger G, Rowe S ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20207F199 | List: |
| References | |
| NUDOCS 9903110193 | |
| Download: ML20207F203 (22) | |
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, l ILLINOIS POWER COMPANY ;
I CLINTON POWER STATION i
)
l l CORE OPERATING LIMITS REPORT I 1 FOR l f RELOAD 6 j CYCLE 7 i i REVISION 1 I J I l l
^
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. Byam%reld Date ue 'RA/RE
. [
.u . - _. f) I .27 ha l%'f S L, Rowe (Reviewer) Date Fuel /PRA/RE J l l blYff FRD / ' 6 ate #
444(M . 4. /IMN Manager-Clinton Powh Static /i Date
- b. k Ae J.V. 5;cek / 2 99 Director-Licensing Date M10009/332 7903110193 990228 7 PDR ADOCK 05000461 j p PDR 2,..
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.: . '; . 1 i
l i INDEX l , l I
)
1 i INTRODUCTION AND
SUMMARY
. . . .. . . ... .. .... . . . . . . . . 3 !
1 l
. I LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.1-AVERAGE .. . . 4 PLANAR LINEAR HEAT GENERATION RATE (APl HGR) l l
}
I LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.2-MINIMUM , . . 12 l 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-REACTOR.... 20 l l PROTECTION SYSTEM (RPS) INSTRUMENTATION SIMULATED THERMAL l POWER TIME CONSTANT l l REFERENCES ... . .. .. .... . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. 21 j i l i l i M10009/332 2 l < i i j.
X l l 1 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 (MCPRr), the core thermal power-dependent { MCPR limits (MCPRp), the LINEAR HEAT GENERATION RATE (LHGR) limits, and f 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 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. l l l
\
i l M10009/332 3 ! I
1 LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.1 l l POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE l l All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR's) for i 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 j 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 j 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 j 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 j Figure 2.1-1, or the core thermal power-dependent MAPLHGR factor (MAPFAC p) of Figure 2.1-2. i
- b. During single recirculation loop operation - l the limits shown in Figures 2,1-3 through 2.1-7 multiplied by the smallest of l MAPFACr, MAPFAC p, or a factor of 0.78 (Reference 5). l l
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CORE FLOW (% RATED), F Figure 2.1-1 Flow-Dependent MAPLHGR Factors (MAPFACf )
=~
CLINTON - UNIT 1 x
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CLINTON - UNIT 1 b / ~ / e -=
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O 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 50,000 55,000 l AVERAGE PLANAR EXPOSURE (mwd ST) Figure 2.1-7 Maximum Avera ge Planar Linear Heat Generation Rate MAPLHGR Limi; Versus Average Planar Exposure - eload 6 uel Type - GE10-P8SXB353-12GZ-120T-150-T l l CLINTON - UNIT 1 **We -' l
LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.2 POWER DISTRIBUTION LIMITS
'f1NIMUM 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 l bundle type as shown in Figures 2.2-la through 2.2-Ic, and the MCPRp limits at indicated l core flow and core THERMAL POWER and AT* as shown in Figures 2.2-2a through l 2.2-2c. These MCPR limits are consistent with Reference 5. J l
i l 1 1 1 i Y
- 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. ( l l { M10009/332 12 l l l
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...,.4 ..a....e.. .4..u..+.. 4' +.4 +a.,.
- i : : ,: . 4. 4 - 4. .a. i a.: ..a - - : i. : : : : 1 : . :
l .,s.q.4...... 4.. 4 ..& . g ,. , .4~. 4. . & - . 6 4. 4. = '4 4 6 a 4.".44 .+4..e-.t..,-.4...s
; r ;; 3. "4. - ;4. 6 ~ 4" - :
- ; - i.. .
. . : ; i : :
i
..j..+ .4,.. 3 9. 9.q... 4...: ..p.
... . 9 .. ..p.. .+.+.a.....q.3..p.4.p: 9.....p.p...q.++~ + t p-r4 .. 7. . 4. ~4.. l
..p.4. . 9 .p..p ..p.q. .... . . 4.. ...y.., ,
...[.. L ..p ~ . ..{..t .4 + 4..{4 * .F. ty .4 4.. .
p.j.% 5 . 4. ..y - 1.0 0 20 40 60 80 100 CORE THERMAL POWER (% RATED), P Figure 2.2-2c Power-Dependent MCPR Limits, AT s50*F and Core Flow 5107%, i Reload Fuel Type GE10 with Bundle Averaged
- Exposure Greater Than 2000 mwd /ST
~
* - = "
l CLINTON - UNIT 1
.. - . ~ . . . . . - - - . . . . . . .. - - - - . . . . . . .- . - - . - ~ - .- .-
*.^ .
j ? LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3.2.3 l POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION 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): l GE8B-P8SQB301-10GZ-120M-150-T , 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 M10009/332 19
.. _ . - -. .. - --= . . . - . - . . . . . - . . - . . . - . . - . - . .
9 LIMITS APPLICABLE TO TECHNICAL SPECIFICATION LCO 3 3.1.1 13J! ACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION SIMULATED THERMAL POWER TIME CONSTANT 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). i 1 t 4 l M10009/332 20
a ~ +- .- - REFERENCES
- 1. CPS Technical Specification 5.6.5, CORE OPERATING LIMITS REPORT l (COLR).
- 2. " General Electric Standard Application for Reactor Fuel" (GESTAR 11),
GE Licensing Topical Report NEDE-24011-P-A, as amended (latest approved version).
- 3. " Maximum Extended Operating Domain and Feedwater Heater Out-of-Sersice l Analysis for Clinton Power Station," GE Report NEDC-31546P, August 1988. l
- 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. I 4.B. " Lattice-Dependent MAPLHGR Report for Clinton Power Station Unit 1 Reload 4, Cycle 5," GE Document 23 A7213 AA, Revision 0, October 1993. l I
4.C " Lattice Dependent MAPLHGR Report for Clinton Power Station Unit 1 Reload 5, Cycle 6," GE Document DRF J11-02425M AP, Revision 0, February 1995. 4.D. " Lattice Dependent MAPLHGR Report for Clinton Power Station Unit I l Reload 6, Cycle 7," GE Document DRF J11-02920 MAP, Revision 1. November 1998.
- 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 I Reload 4 Cycle 5," GE Document 23A7213, Revision 0, October 1993. ! l 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. , I 5.D. " Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 6 Cycle 7," GE Document DRF J11-02920SRLR, Revision 2, November 1998.
- 6. Letter to J. S. Charnley (GE) from C. O. Thomas (NRC), " Acceptance for Referencing ofLicensing Topical Report NEDE-24011-P-A-6, Amendment 10,
' General Electric Standard Application for Reactor Fuel'," MFN-082-85, May 28, 1985 i
i M10009/332 21 ;
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l
.s
- P j
- 7. Letter to J. S. Charnley (GE) from A. C. Thadani (NRC), " Acceptance for Referencing of Amendment 18 to General Electric Licensing Topical Report i NEDE-24011-P-1, ' General Electric Standard Application for Reactor Fuel'," hiay )
12,1988.
- 8. Letter to Nuclear Regulatory Commission from J. S. Peny (IP), "Clinton Power '
Station Proposed Amendment of Facility Operating License No. NPF-62," ) U-602085 [LS-92-004], February 11,1993. l
- 9. Letter to F. A. Spangenberg (IP) from D. V. Pickett (NRC), " Issuance of !
Amendment [No. 75] (TAC No. h185816)," May 25,1993.
- 10. . Letter to J. A. Miller (IP) from R. D. Williams (GE), " Simulated Thermal Power hionitor," RDW:95-160, November 16,1995.
l l i hi10009/332 22
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