ML042880472

Core Operating Limits Report- Revision 13

ML042880472
Person / Time
Site:	Palisades
Issue date:	10/07/2004
From:	Domonique Malone Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML042880472 (12)

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CdN Palisades Nuclear Plant Committed to NcaE ct Operated by Nuclear Management Company, LLC October 7, 2004 Technical Specification 5.6.5 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Core Operating Limits Report- Revision 13 Nuclear Management Company, LLC is providing revision 13 of the Palisades Core Operating Limits Report (COLR). This report is submitted in accordance with the requirements of Palisades Technical Specification 5.6.5.d. Enclosure 1 contains a summary of changes from the previous revision and enclosure 2 contains revision 13 of the COLR.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

Daniel J. Malone Site Vice-President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosures (2) cc: Administrator, Region l1l, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC /Noo 27780 Blue Star Memorial Highway

• Covert, Michigan 49043-9530 Telephone: 269.764.2000

ENCLOSURE I PALISADES CORE OPERATING LIMITS REPORT REVISION 13

SUMMARY

OF CHANGES In section 2.1.3, the words "for normal cooldowns and heatups' are removed because normal cooldowns and heatups do not occur in Mode 5, loops not filled.

In Table 2.4-1, peaking factor limits for all other fuel types are changed to 2.04 for the entire cycle.

In section 2.6.b, the maximum cold leg temperature is changed to 544 0F, as required, to use the statistical setpoints methodology EMF-1961 (P)(A), revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," listed in Technical Specification Section 5.6.5.

Page 1 of 1

ENCLOSURE 2 PALISADES CORE OPERATING LIMITS REPORT Revision 13 9 Pages Follow

y Procedure No COLR Revision 13 Issued Date 10/512004 PALISADES NUCLEAR PLANT TITLE: CORE OPERATING LIMITS REPORT 2? E I V// ,/0Li Preparer" Date ThnicaReview I / Date I o/0 ' / So ° i- ,,a O PRC Reviewed Date Reference #

/ t//

Reactor Engineering Supervisor Date

Palisades COLR Revision 13 Page 1 of 8 Consumers Energy Company Nuclear Management Company, LLC Docket No 50-255 License No DPR-20 Core Operating Limits Report

1.0 INTRODUCTION

This Core Operating Limits Report for Palisades has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Technical Specifications Limiting Conditions for Operation (LCOs) affected by this report are listed below:

Section Title LCO 2.1 SHUTDOWN MARGIN (SDM) 3.1.1 3.1.6 3.9.1 2.2 Regulating Rod Group Position Limits 3.1.6 2.3 Linear Heat Rate (LHR) 3.2.1 2.4 Total Radial Peaking Factor 3.2.2 2.5 AXIAL SHAPE INDEX (ASI) 3.2.4 2.6 PCS Pressure, Temperature, and Flow 3.4.1 Departure from Nucleate Boiling (DNB) Limits

Palisades COLR Revision 13 Page 2 of 8 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 SHUTDOWN MARGIN (SDM) 2.1.1 MODES 1 and 2 (LCO 3.1.6 Regulating Rod Group Position Limits) - The minimum SDM requirement is 2% with the most reactive rod fully withdrawn. The rod insertion limit (PDIL) is discussed in Section 2.2 and shown in Figure 2.2-1.

2.1.2 MODES 3, 4 and 5, Loops Filled (LCO 3.1.1 SHUTDOWN MARGIN) - The SDM requirement is 2 2% for normal cooldowns and heatups.

2.1.3 MODE 5, Loops Not Filled (LCO 3.1.1 SHUTDOWN MARGIN) - The SDM requirement is 2 3.5% assuming Ta,. of 60 0F.

2.1.4 MODE 6 (LCO 3.9.1 Boron Concentration) - The SDM requirement is specified in the definition of REFUELING BORON CONCENTRATION.

2.2 Regulating Rod Group Position Limits

a. If the reactor is critical, 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 2.2-1.

b. 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 Group 2 at 72 inches (ie, - 45% control rod insertion)

c. The sequence of withdrawal of the regulating groups shall be 1, 2, 3, 4.

d. An overlap of control banks in excess of 40% shall not be permitted.

Palisades COLR Revision 13 Page 3 of 8 POWER DEPENDENT INSERTION LIMITS IWUR PUMP OPERATON 100.

S II I I I I I I I I I 0 s 30 10 i_ _OPERATING REGIONl l -

20 I_ ii ii 1 I TI I I11 132 8s R 4 40 0 132 GROP2 80 60 132 S0 GROUP 48 o CONTROL ROD POSITION (inches widxrawn)

Figure 2.2-1 Regulating Rod Group Position Limits NOTE: A regulating rod is considered fully withdrawn at >128 inches.

I-Palisades COLR Revision 13 Page 4 of 8 2.3 Linear Heat Rate (LHR)

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

LHR < LHRTSx FA(Z)

Where:

LHRTS= Maximum allowable LHR shown in Table 2.3-1.

FA(Z) = Allowable LHR as a function of peak power location shown in Figure 2.3-1.

I Peak Rod  !

Table 2.3 Linear Heat Rate Limit 15.28 (kW/ft)

To ensure that the design margin of safety is maintained, the determination of both the incore alarm setpoints and the Allowable Power Level takes into account the local LHR measurement uncertainty factors given in Table 2.4-2, an engineering uncertainty factor and a thermal power measurement uncertainty factor (values given in Technical Specification Basis B 3.2.1).

1.2 Unacceptable E1.1 Operation (0.60, 1.00)

E11.0 4 ,

I i 1 oO.9 (1.00, 0.93) 2Co Acceptable Operation 20.8 0.7 0.7 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Active Fuel IHeIght Figure 2.3 Allowable LHR as a Function of Peak Power Location

1 Palisades COLR Revision 13 Page 5 of 8 2.4 Total Radial Peaking Factor The radial peaking factor shall not exceed the following:

for P > 0.5 Fr < FrS x[1.0+0.3x(1- P)]

and for P < 0.5, FF<rSX I15 Where:

Fr = Measured Fr 9 FTS Peaking Factor Limits (Table 2.4-1),

P = Fraction of rated power.

Table 2.4 Peaking Factor Limits, FTs I

All Other Fuel Types 2.04 I To ensure that the design margin of safety is maintained, the determination of radial peaking factors takes into account the appropriate measurement uncertainty factors given in Table 2.4-2.

Palisades COLR Revision 13 Page 6 of 8 TABLE 2.4-2 POWER DISTRIBUTION MEASUREMENT UNCERTAINTY FACTORS 2.5 AXIAL SHAPE INDEX (ASI)

The ASI limit for the Tiniet function is shown in Figure 2.5-1.

1.2 1.1 Z o.

j l iacceptabb a 1.0 Operation 0o.e

~0.8 o Operation 0.6 0

~0.5 0.3 0.2

-0.600 -0.400 -0.200 0.000 0.200 0.400 AxIal Shapo Index Figure 2.5 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

+0.400, 0.250

t Palisades COLR Revision 13 Page 7 of 8 2.6 PCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits

a. Pressurizer pressure 2 2010 psia and < 2100 psia

b. PCS cold leg temperature < 544 OF I C. PCS total flow rate 2 352,000 gpm

Palisades COLR Revision 13 Page 8 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 Technical Specification Section 5.6.5 list of methodology documents. Specific application of these methodologies to Palisades is described in the cycle's most current safety analysis reports.

The analytical methods used to determine the radial peaking factor measurement uncertainty factors are described in FSAR, Section 3.3.2.5.