ML18064A859

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Rev 1 to Palisades Core Operating Limits Rept.
ML18064A859
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/04/1995
From: Bates M, Duffy T
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18064A858 List:
References
NUDOCS 9508150253
Download: ML18064A859 (10)
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Text

Pali sades COLR Rev i s ion 1

  • Date 8-9-95 PALISADE.S PLANT CORE OPERATING LIMITS REPORT I '6- L./-9S Preparer *Date Date PR Oate Reference #

al

~50~150253 9508b~

PDR ADOCK 05000255

  • :* ~---- . . -_PDR - * * - ,J '

Pa 1i sades COLR Revision 1 Page 1 of 9 Consumers Power Company Docket No. 50-255 License No. DPR-20 Core Operating Limits Report

.1.0 GORE 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 Technital Specificattons affected by this report are listed below:

Section Specification 2 * .1 ASI Limits for T;niet Function 3 .1.1 2.2 Regulating Group Insertion Limits 3 .10 ..5 2.3 Linear Heat Rate (LHR) Limits 3.23.1 2.4 Radial Peaking Factor Limits 3.23.2 NOTE:

Any protedure or document previously referencing the Technfcal 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.

  • Pali sades COLR Revision I Page 2 of 9 2.0 OPERATING LIMITS The cycle specific parameter limi~s for the specifications listed in Section I 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 Tinll1 Function(Technical Specification 3.1.1)

The ASI limit for the Tinllt function is shown in Figure 2.1.

. i.

i I

1.2 1.1 i I

j 1  !

I Unacceptable I i 0.9 ~

I i

Operation 0

Q, Ill 0.8

' Acceptable I

iii Operation a:: 0.7 0

c

_g 0.6 1 J

ti

...."' 0.5 ~

I 0.4 1 0.3 .

0.2

-0.6 -0.4 . -0.2 0 0.2 0.4 0.6 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, 1.080

+0.400, 1.080

+0.400, 0.250

a. To implement the limits ~n shutdown margin, individual rod worth and hot channel factors, the limits on
  • established as shown on Figure 2.2.
b. The sequence of withdrawal of the regulating groups shall be l, 2, 3, 4.
c. An overlap of control banks in excess to 403 shall not be permitted.

~-- -- -------------------- - - - - - - -

~-------

d. If the reactor is. subcritic~l, the rod position at which criticality could be achieved 1f the control rods were withdrawn in normal sequence shall not be lower than the insertion limit for zero power shown on Figure 2.2.
  • Pali sades COLR Revision 1 Page 4 of 9

--*- .- - ---.~-- --

  • I TWO

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-..........__ ----- MAX--~UL~IL I

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0

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  • .oo 0 20 40.._ <!!". IO

~ "DO.......,..,... WINI' Figure 2.2 *Power Dependent Controt Rod lnMl'tlon Limit

Pali sades COLR Revision 1 Page 5 of 9 2.3 Linear Heat Rate CLHR) Limits (Technical Specification 3.23.1)

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

Where:.

LH Rrs = Maximum allowable LHR shown in Table 2.1.

FA(Z) = Allowable LHR as a function of peak power location s~own in Figure 2.3.

.,----___:.-----------.---ra-b-n~--t.-1----nnearHear-RafeTTmf f ___ _

Peak Ro.d 15.28 (kW/ft)

II II

Pali sades COLR Revision 1 Page 6 of 9 1.2

~ Unacceptable .- -

3 1.1 Operation

  • I

~

0 1.0 (0.60, 1.00)

I..

!!:. 0.9 Accep:a*

Operation (1.00, 0.93) 3 IJ 0.8

~

0.7 ,___ _ _......._ _ _....,,_ _ _ _ _ _ _ _ ___.._ _ _ __,

0.0 0.2 0.4 0.6 0.8 1.0 Frw:doft of Active Fuel tt91g11t*

Figure 2.3 - Allowable LHR as a Function of Peak Power.Location

.* Pa 1 i sades COLR Revision 1 Page 7 of 9 2.4 Radial Peaking Factor Limits (Technical Specification 3.23.2)

The radial peaking factor shall not exceed the following:

for P ~ 0. 5 rs F. =F, x [1.0 +0.3 x (1 -P)]

and for P < 0.5, Fr = F1rs x 1

  • 15 Where:

F. = Measured F~ or F~ ,

F1~

r = Maximum allowable F~ or F~ (Table 2.2),

p = rraction of rated power.

Table 2.2 - Peaking Factor Limits ' F rs

- r Peaking Factor Reload L & M Reload N Reload 0 & p Assembly FAr . 1. 57 1. 66 1. 76 Peak Rod F1r 1. 92 1. 92 2.04

  • J. ... ~*
  • Revision 1 Page .8 of 9 3.b ANALYTICAL METHODS.

The analytical methods used to determine the core operating limiis 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 Compahy, dated April 1977, Supplemeht 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 ~nd Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Methodology for Pressu~ized Water Reactors: Analysis of Chapter 15 Events~" Advanced Nuclear Fuels Corpor~tion, Qctobe~ 1990.

3.3 XN~NF-82-21(P)(A), Revision 1, "Application of Exxon Nuclear Co~pany PWR

  • Thermal Margin,Methodology to Mixed Core Configurations," Exxon .

Nuclear Company, September 1983.

  • 3.t ANF-84-093(P)(A}; and Supplement l, "Steamline Break Methodology for PWRs," Advanced Nuclear Fuels Corporation, March 1989.

3.5 XN-75-3Z(P)(A), Supplem~nts 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.

~ ._, .. ..

  • Pali sades COLR Revision 1 Page 9 of 9 3.6 EXEM PWR Large Break LOCA Model as def1ned by:

XN-NF-82-20CA), Revision 1 and Supplements 1 throu~h 4, "Exxon Nuclea~

Comp~ny 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, No_vember 1982.

XN-NF-81-58(~). 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-.8 5 - 16 ( A) ,

  • Vo 1 um e 1 , Sup p1em en t s 1 t h r o ugh 3 , a nd Vo l um e 2 ,

Revision 1 and Supplement 1, "PWR 17x17 Fuel Cooling Te~ts Program," Exxon Nuclear Company, February 1990.

XN-NF-85-lQS(A), and Supplement 1, "Scaling of FCTF Based Reflood Hea.t

- *Tran~fer C~rrelation for other Bundle Designs," Exxon Nuclear Companj, Jariuary 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.~ ANF-1224(P)(A), and Supplement 1, "Dep~rture from Nucle~te Boiling Correlation for High Thermal Performance Fuel," Advanced Nuclear Fuels Corporati.on, April 1990.
  • 3.9 ANF-89-151(P)(A), "ANF-RELAP ~ethodology for Pres~uriz~d Water Reactors:

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

  • 3.lo fMF-92-153(P)CA), "HTP: Departure from Nucleate ~oiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation.

Specifi~ application of these meth6dologies to Palisad~s is ~escribed in EMF-95-016 Rev. 1, "Palisades Cycle 12 Safety Analysis Report," dated July 1995 ..

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