ML072820336
| ML072820336 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/09/2007 |
| From: | Schwarz C Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML072820336 (12) | |
Text
Enlergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 October 9, 2007 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 15
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. is providing revision 15 of the Palisades Nuclear Plant (PNP) Core Operating Limits Report (COLR). This report is submitted in accordance with the requirements of PNP Technical Specification 5.6.5.d. Enclosure 1 contains a summary of changes from the previous revision. Enclosure 2 contains revision 15 of the COLR.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Site vice President Palisades Nuclear Plant CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
ENCLOSURE "B PALISADES CORE OPERATING LIMITS REPORT REVISION 15
SUMMARY
OF CHANGES Section 2.4, "Total Radial Peaking Factor" is revised to include a requirement to evaluate pin powerlburnup of the core design against certain criteria. This change satisfies a commitment made in a September 21, 2007, letter from Entergy Nuclear Operations Inc. (ENO) to the Nuclear Regulatory Commission. EN0 made the commitment in support of a license amendment request to implement a full-scope alternative source term methodology at Palisades Nuclear Plant.
Page one includes an administrative change to reflect the current owner and operator of Palisades Nuclear Plant (Entergy Nuclear Palisades, LLC, and Entergy Nuclear Operations, Inc., respectively).
Page 1 of 1
ENCLOSURE 2 PALISADES GORE OPERATING LIMITS REPORT REVISION 15 9 Pages Follow
Procedure No GOLR Revision 15 Issued Dale 10\\09/2007 PALISADES NUCLEAR PLANT T%TLE: CORE OPERATING LIMITS REPORT Reactor Engineering Supervisor Date
Palisades C 8 L R Revision 15 Page 1 sli 8 Eatergy Nuclear Palisades, hbC Enlergy Nuclear Operations, Inc.
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 2.1 SHUTDOWN MARGlN (SDM) 2.2 Regulating Rod Group Position Limits 2.3 Linear Heat Rate (LHR) 2.4 Total Radial Peaking Factor 2.5 AXIAL SHAPE INDEX (ASI) 2.6 PCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
Palisades GOL-R Revision 15 Page 2 of E 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.I.l MODES 1 and 2 (LC0 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 (LC0 3.1.1 SHUTDOWN MARGIN) - The SDM requirement is 2 2% for normal cooldowns and heatups.
2.1.3 MODE 5, Loops Not Filled (LC0 3.1.1 SHUTDOWN MARGIN) - The SDM requirement is 2 3.5% assuming T,,,
of 60°F.
2.1.4 MODE 6 (LC0 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 CBLR Revision 15 Page 3 o-f 8 POWER DEPENDENT INSERTION LIMITS FOUR PUMP OPERATION I
I 132 I
GROUP3 40 d
CONTROL ROD POSITION (inches withdrawn)
Figure 2.2-1 Regulating Rod Group Position Limits NOTE:
A regulating rod is considered fully withdrawn at 2128 inches.
P
Palisades COLR Revisio!~ 15 Page 4 of 8 Linear Heat Rate (LHR)
The LHW in the peak powered fuel rod shall notexceed the following:
Where:
LH RTS =
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.
Tablie 2.3 Linear Heat Rate Limit 1
I I[
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 LI-IR 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).
Peak Rod Unacceptable meration (0.60, 1.80)
Acceptable Operation Fraction of Active Fue I 8-b lght Figure 23 Allowable LHR as a Fundon of Pegk Power 15.28 (kW/ft)
Palisades 68hR Revisioiis 15 Page 5 of 8 2.4 To-i-al Radial Peaking Factor The radial peaking factor shall not exceed the following:
for P 2 0.5 F,. < F:~X[~.O+O.~X(~-P)]
and for P < 0.5, Fr I ~ J ~ x l
.1 5 Where:
Fr Measured F::,
Peaking Factor Limits (Table 2.4-1 ),
P Fraction of rated power.
Table 2.4 Peaking Factor Limits, F:~
All Fuel Types 2.04 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.
To ensure that the design margin of safety is maintained with respect to the alternative source term radiological consequence analysis assumptions as restricted by footnote 11 of Table 3 of Regulatory Guide 1.183, an evaluation shall be performed on "re pin powerlburnup of the core design against the following criteria:
Fewer than 21 rods in any one assembly violate the "5416.3" criterion.
Fewer than 20 assemblies in any core design contain at least one rod that violates the "5416.3" criterion.
All rods that violate the "5416.3" criterion have a rod average linear heat generation rate of less than 6.7 kWlft.
All rods that violate the "5416.3" criterion have a rod burnup of less than 58.5 GWDIMTU.
In any assembly containing any rods that violate the "5416.3" criterion there are at least four times as many rods that have total radial peaking factor of less than % of the total radial peaking factor limit of 2.04.
Palisades 60LW Revision 15 Page 6 of 8 TABLE 2.4-2 POWER DISTWIBUTIOiI MEASUREMENT UNGERTAilNTV FACTORS AXIAL SHAPE INDEX (ASI)
The AS1 limit for "re Tinlet function is shown in Figure 2.5-1 LHR
~r '
Axial Shape lndex Measurement Uncertainty Break Points:
-0.550, 0.250
-0.300, 0.700
-0.080, 1.OOO
-0.080, 1.065
+0.400, 1.065
+0.400, 0,250 0.0500 0.0425
Palisades COLR Revision 15 Page 7 of 8 2.6 PCS Pressure, Temperature, and Flow Departure from Nucleak Boiling (DNB)
Limits
- a.
Pressurizer pressure 2 201 0 psia and 1 21 00 psia
- b.
PCS cold leg temperature i 544 OF C.
PCS total flow rate e 352,000 gpm
Palisades CObR Reviaion 15 Page 8 af 8 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.