ML18066A758

Rev 3 to Palisades Colr.

ML18066A758
Person / Time
Site:	Palisades
Issue date:	12/04/1996
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18066A757	List: ML18066A756 ML18066A758
References
NUDOCS 9612170342
Download: ML18066A758 (10)

Text

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CONSijMERS POWER COMPANY PAlISAD.E.S PLANT DOCKET 50--255 PALISADES CORE LIMITS REPORT Revi s*i on 3 ---------------------------------------

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--*--------9612170342 961210 i I PDR ADOCK 05000255;.

p PDR[_J e PALISAPES PLANT e Palisades COLR Revision 3 .Date CORE OPERATING LIMITS REPORT lMJ 1lf-OU?b itif76 TechnpalReviewer Preparer

• Date . 11J/'t/111 96-;i.ub C Reviewed Date

• Reference

1. -:?' IU'( 1'1" I Nuclear Engineering Supervisor Approval Date -------------------------------

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• Consumers Power Company Docket No. 50-255 License No. DPR-20 Core Operating Limits Report 1.0 CORE OPERATING LIMITS REPORT Palisades COLR Revision 3 Page 1 of 8 This Core Operating Limits Report for Palisades has been prepared in accordance with the requirements of Technical Specification 6 . 6 . 5 .

The Technical Specifications affected by this report are listed below: Section 2.1 2.2 2.3 2.4 NOTE: Title AS! Limits for Tinlet Function Regulating Group Insertion Limits Linear Heat Rate (LHR) Limits Radial Peaking Factor Limits Specification 3 .1.1 3.10.5 3.23.1 3.23.2 Any procedure or document previously referencing the Technical Specifications for any operating limit that has been moved to the COLR should be viewed as referencing the COLR until the applicable procedures or documents are revised.

' . 2.0 OPERATING LIMITS Palisades COLR Revision 3 Page 2 of 8 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 ASI Limits for T.inlfil Function(Technical Specification 3.1.1) The ASI limit for the Tinlet function is shown in Figure 2 .1. 1.2 1.1 .. 1.0 CD :r: 0.9 0 a. ,, 0.8 CD .. ca 0.7 a: .... 0.6 0 c 0 0.5 :;::; u 0.4 e u.. 0.3 0.2 -0.600 Break Points: -0.550, 0.250 -0.300, 0.700 Unacceptable Operation

-0.400 -0.200 Acceptable Operation 0.000 0.200 Axial Shape Index 0.400 Figure 2.1 -ASI Limit for Tinlet Function . _____ :::_O. 0_8_0_, _____ l ....... .QO.Q ______________________

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1 -0. 080, 1.080 +0.400, 1.080 +0.400, 0.250

. ' ' . Palisades COLR Revision 3 Page 3 of B 2.2 Regulating Group Insertion Limits (Technical Specification

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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 of 40% shall not be permitted.

d. The reactor shall not be made critical with a control rod position lower than the insertion limit for zero power shown on Figure 2.2. --------------...... -----------------------

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' . .... eo i 50 .,, c.. QO ""

• 30 i 2.0 "' 10 0 Clril 0 100 90 l 80 g 70 iO I.I. 60 0 -i 50 qo IX !=? so ... w IZf 2() 10 00

• TWO OR THRE:E PUMP 0-PERATIOtt

.. MAX I MUM POWER LEV£L Palisades COLR Revision 3 Page 4 of 8 20 1K1 60 SO I CO O 20 1Ht0&) Q() GROUP @ g---_....ro----+-Ji---+es-----tJo!o---""""'l,Jo toNTftOL liOD IHSERTIOM.

PERCEJIT 6ROU, @ F-OUR PUMP OP£RATlmt 20 20 &RO@ 40 Jo 1Jo 100 0 GltOllf> @ 6 10 Jo GROUP Jo CONTROL ROD l NSERTIQN, PERCatT @. ------------------------------------------* --------* ------Figure 2.2 Power Dependent Control Rod Insertion Limits

• Palisades COLR Revision 3 Page 5 of 8 2.3 Linear Heat Rate (LHR) Limits (Technical Specification 3.23.1) The LHR in the peak powered fuel rod shall not exceed the following:

Where: LHR LHRTs x FA (z) Maximum allowable LHR shown in Table 2.1. Allowable LHR as a function of peak power location shown in Figure 2.3. Table 2.1 -Linear Heat Rate Limit Peak Rod 15.28 (kW/ft) 1.2 1.1 J: ..J " E J: :i 1.0 ..J E .g :IE .... 0.9 £! 0 Ci c 0 ., " f! 0.8 !:!:. 0.7 0.0 0.2 Unacceptable Operation Acceptable Operation 0.4 0.6 (0.60, 1.00) Fraction of Active Fuel Height (1.00, 0.93) 0.8 1.0 Figure 2.3 -Allowable LHR as a Function of Peak Power Location

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• Palisades COLR Revision 3 Page 6 of 8 2.4 Radial Peaking Factor Limits (Technical Specification 3.23.2) The radial peaking factor shall not exceed the following:

for PL 0.5 Fr = FrTS X [1.0 + 0.3 X (1-P)] and for P < 0.5, Where: pTS r Maximum allowable FA or FT (Table 2.2), r r p Fraction of rated power. Table 2. 2 -Peaking Factor Limits, FrTs Peaking Factor Reload M Reload N Reload 0 & Later Assembly FA 1. 57 1. 66 1. 76 r Peak Rod FT 1. 92 1. 92 2.04 r *---*------**-

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• Palisades COLR Revision 3 Page 7 of 8 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 Supplements 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 B and 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 3.4 3.5 Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983. ANF-84-093 ( P) (A) , and Methodology for PWRs, March 1989. Supplement 1, "Steamline Break " Advanced Nuclear Fuels Corporation, XN-75-32 (P) (A), Supplements 1 Procedure for Evaluating Fuel Company, October 1983. through 4, Rod Bowing," "Computational Exxon Nuclear 3.6 EXEM PWR Large Break LOCA Model as defined by: ----

and-supp-i-ements---1--through--4-,--

-"Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, January 1990.

• Palisades COLR Revision 3 Page 8 of *8 XN-NF-82-07 (P) (A), Revision 1, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, November 1982. 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 Volume 2, Revision 1 and Cooling Tests Program," 1990. 1, Supplements 1 through 3, and Supplement 1, "PWR 17xl 7 Fuel Exxon Nuclear Company, February XN-NF-85-105(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-89-151 (P) (A), "ANF-RELAP Methodology for Pressurized Water Reactors:

Analysis of Chapter 15 Events, " Advanced Nuclear Fuels Corporation, April 1992. 3 .10 EMF-92-153 ( P) (A) , "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation.

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Specific of these methodologies to Palisades is described in the cycle's most current Safety Analysis Report.