ML18059A944

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Proposed Rev 0 to Palisades Colr.
ML18059A944
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/04/1994
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18059A942 List:
References
NUDOCS 9404190247
Download: ML18059A944 (14)
v • d • e


Text

ATTACHMENT 3 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED CORE OPERATING LIMITS REPORT April 7, 1994

  • 13 Pages

Pali sades COLR Revision 0 Date 4-4-94 PALISADES PLANT CORE OPERATING LIMITS REPORT Date

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Pali sades COLR Revision 0 Page 1 of 12 Consumers Power Company Docket No. 50-255 License No. DPR-20 Core Operating Limits Report 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for Palisades has been prepared in accordance with the requirements of Technical Specification 6.9.1 (f). The Technical Specifications affected by this report are listed below:

Section Title SQecification 2.1 Tinlet Function and ASI Limits 3 .1.1 2.2 Regulating Group Insertion Limits 3.10.5 2.3 Excore Monitoring Allowable Power Level 3.11.2 2.4 Linear Heat Rate (LHR) Limits 3.23.l 2.5 Radial Peaking Factor Limits 3. 23. 2 -

Palisades COLR Revision 0 Page 2 of 12 2.0 OPERATING LIMITS The cycle specific parameter limits for the specifications listed in Section 1 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Section 3.0.

2.1 Iin~t Function and ASI Limits (Technical Specification 3.1.1)

During steady state operation, the reactor inlet temperature shall not exceed the value determined by the following equation:

Tinlet5;542.99 +0.0580(P -2060)+0.0000l(P -2060) 2 +L125(W-138)-0.0205(W-138):2 Where Tinlet Reactor inlet temperature in ° F, P Nominal operating pressure in psia, W Total recirculating mass flow in 106 lbm/hr corrected to operating temperature conditions.

The limits of validity of this equation are:

  • 1800 ~ Pressure ~ 2200 psia 100 x 106 ~ Vessel Flow ~ 150 x 10 6 lbm/hr ASI as shown in Figure 2.1 If measured primary coolant flow rate is greater than 150 M lbm/hr, the maximum reactor inlet temperature shall be less than or equal to the Tinlet LCO at 150 M lbm/hr.
  • This effectively increases the margin to DNB at high PCS fl ow rates .

Pal is ades COLR Revision O Page 3 of 12 The AS! limit for the Tinlet function is shown in Figure 2.1.

1.2 --~--~-~----~-~--~-~--~-~-~

1.1

~ 0.9 Unacceptable Operation

~

"'O 0.8 20 0::: 0.7 Acceptable 0 Operation

§ 0.6

e

~ 0.5 0.4 0.3 0.2 L._...._---1...._ _1....-._ __i___ _ _ J t . , _ _ _ . . . J . . __ _ _ ._ _...J..__ _ _ ._ __.___ _ __ _ _ .

-0.6 -0.5 -0.4 -0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 0.4 0.5 Axial Shape Index Figure 2.1 - ASI Limit for TinLet Function Break Points:

-0.550, 0.250

-0.300, 0.700

-0.080, 1.000

-0.080, 1.065

+0.400, 1.065

+O .400, 0.250

Palisades COLR Revision 0 Page 4 of 12 2.2 Regulating Group Insertion Limits (Technical Specification 3.10.5)

a. To implement the limits on shutdown margin, individual rod worth and hot channel factors, the limits on control rod regulating group insertion shall be established as shown on Figure 2.2.
b. The sequence of withdrawal of the regulating groups shall be 1, 2,- 3, 4.
c. An overlap of control banks in excess to 40% shall not be permitted.
d. If the reactor is subcritical, the rod position at which criticality could be achieved if the control rods were withdrawn in normal sequence shall not be lower than the insertion limit for zero power shown on Figure 2.2.

Pa 1is ades COLR Revision 0 Page 5 of 12

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TWO CA THRE! P\JMP OPERATION eo

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-............._ - MAXIMUM POWER LEVEL

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20 uc 10

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0 0

80 100

  • 100 90 FOUR PUMP OPERATION

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.... ~ ..______,.______,.._______+-______,,.~0

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0 20 eo 100 Figure 2.2 *Power Dependent Control Rod Insertion Limit

Palisades COLR Revision 0 Page 6 of 12 2.3 Excore Monitoring Allowable Power Level (Technical Spec~fication 3.11.2)

The Excore Monitoring Allowable Power Level (APL) is determined as follows:

LHR(Z) 15 ]

APL = x Rated Power

.[ LHR(Z)Max x V(Z) x 1.02 _

M1n Where:

(1) LHR(Z) 15 is the limiting LHR vs. core height (Section 2.4),

(2) LHR(Z)Max is the me~sured peak LHR vs. core height which includes

. the uncertainties listed in Table 2.1, (3) V(Z) is the function shown in Figure 2.3, (4) The factor of 1.02 is an allowance for the effects of upburn, (5) The quantity in brackets is the minimum value for the entire core at any elevation (excluding the top and bottom 10% of the core) considering limits for peak rods. The upper limit on the value of APL is 1.0 x Rated Power.

  • Palisades COLR Revision 0 Page 7 of 12 Table 2.1 - Power Distribution Uncertainty Factors Measurement Measurement Measurement Peaking Parameter Uncerta i nt~/a> Un cert a i nty Uncerta i nty<c>

LHR 0.0623 0.0664 0.0795 FAr 0.0401 0.0490 0.0695 FTr 0.0455 0.0526 0. 0722 (a) Uncertainty for reload cores using all fresh incore detectors.

(b) Uncertainty for reload cores using a mixture of fresh and once burned incore detectors.

(c) Uncertainty when quadrant power tilt, as determined using incore measurements and incore analysis computer program (see FSAR Section 7.6.2.4), exceeds 2.8% but is less than or equal to 5%.

1.18 1.16 (0.94, 1.15)

(1.00, .15) 1.14 1.12 1.10 o.oo, 1.11) (0.77, 1.11) t:J, 1.08 1.06 1.04 1.02 0.98 .___ __.__ __.___ __._ ___.__ _...___ __,__ _.....___ ____._ ___.__ __.

0 0.1 0.2 0.3 0.4 0.5 0.6 . 0.7 0.8 0.9 Bottom Fraction of Active Fuel Height Top Figure 2.3 - Axial Variation Bounding Condition

Pa 1i sades COLR Revision O.

Page 8 of 12 2.4 Linear Heat Rate (LHR} Limits (Technical Specification 3.23.1)

The LHR in the peak powered fuel rod shall not exceed the following:

. LHR ~ Lffll.rs x FA(Z)

Where:

LHRTS = Maximum allowable LHR shown in Table 2.2.

FA (Z) Allowable LHR as a function of peak power location shown in Figure 2.4.

Table 2.2 - Linear Heat Rate Limit Peak Rod 15.28 (kW/ft)

Pa 1i sades COLR Revision 0 Page 9 of 12

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_J 1.1 Unacceptable E Operation

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  • x0
? (0.60, 1.00)

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0 (1.00, 0.93)

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0.7 ~~-~~-~~~~~-~~~--------------~

0 0.2 0.4 0.6 0.8 Fraction of Active Fuel Height Figure 2.4 - Allowable LHR as a Function of Peak Power Location

Pali sades COLR Revision O Page 10 of 12 2.5 Radial Peaking Factor Limits (Technical Specification 3.23.2)

The radial peaking factor shall not exceed the following:

for P ~ 0.5 TS fr = fr X [ 1. 0 + 0. 3 X (I - P ) ]

and for P < 0.5, Where:

Fr = Measured F~ or F~ ,

F~ Maximum allowable F~ or F~ (Table 2.3),

5 P Fraction of rated power.

Table 2.3 - Peaking Factor Limits, FTS r Peaking Factor Reload L &M Reload N Reload 0 Assembly FAr 1.57 1.66 1. 76 Peak Rod FTr 1.92 1. 92 2.04

Pal is ades COLR Revision 0 Page 11 of 12 3.0 ANALYTICAL METHODS The analytical methods used to determine the core operating limits are those previously reviewed and approved by the NRC, specifically those described in the following documents:

3.1 XN-75-27(A), and Suppleme~ts 1 through 5, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, dated April 1977, Supplement 1 dated September 1976, Supplement 2 dated December 1980, Supplement 3 dated September 1981, Supplement 4 dated December 1986, Supplement 5 dated February 1987.

3.2 ANF-84-73(P)(A), Revision 5, Appendix Band. Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Methodology for Pressurized

.water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation, October 1990.

3.3 XN-NF-82-21(P)(A), Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.

3.4 ANF-84-093(P)(A), and Supplement 1, "Steamline Break Methodology for PWRs," Advanced Nuclear Fuels Corporation, March 1989.

3.5 XN-75-32(P)(A), Supplements 1 through 4, "Cbmputational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.

3. 6 EXEM PWR~,-Large Break LOCA Mode 1 as defined by:

XN-NF-82-20(A), Revision 1 and Supplements 1 through 4, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, January 1990.

XN-NF-82-07(P)(A), Revision 1, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, November 1982.

_ ___J

Pal i sades COLR Revision O Page 12 of 12 XN-NF-81-58(A), Revision 2 and Supplements 1 through 4, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, Revision 2 and Supplements 1 and 2 dated March 1984, Supplements 3 and 4 dated June 1990.

XN-NF-85-16(A), Volume 1, Supplements 1 through 3, and Volume 2, Revision 1 and Supplement 1, "PWR 17xl7 Fuel Cooling Tests Program," Exxon Nuclear Company, February 1990.

XN-NF-85-44(A), and Supplement 1, "Scaling of FCTF Based Reflood Heat Transfer Correlation for other Bundle Designs," Exxon Nuclear Company, January 1990.

3.7 XN-NF-78-44(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983.

  • 3.8 ANF-1224(P)(A), and Supplement 1, "Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Advanced Nuclear Fuels Corporation, April 1990.

3.9 ANF-89-192(P), "Justification of the ANFP DNB Correlation for High Thermal Performance Fuel in the Palisades reactor," Advanced Nuclear Fuels Corporation, January 1990.

3.10 ANF-89-15l(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactots:

Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, April 1992.

3.11 EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal* Performance Fuel," Siemens Power Corporation.

Specific application of these methodologies to Palisades is described in EMF-92-177, "Palisades Cycle 11 Safety Analysis Report," dated August 1993.

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