ML031480579
| ML031480579 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/15/2003 |
| From: | Cooper D Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML031480579 (12) | |
Text
Committed to Nuclear Excellen Palisades Nuclear Plant Operated by Nuclear Management Company, LLC May 15, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 PALISADES NUCLEAR PLANT DOCKET NO. 50-255 LICENSE DPR-20 CORE OPERATING LIMITS REPORT - REVISION 11 Nuclear Management Company, LLC is providing revision 11 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. Attachment 1 contains a summary of changes from the previous revision and attachment 2 contains revision 11 of the COLR.
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
Douglas E. Cooper Site Vice-President, Palisades cc: Regional Administrator, USNRC, Region IlIl Project Manager, USNRC, NRR NRC Resident Inspector, Palisades Attachments 27780 Blue Star Memorial Highway
- Covert, Ml 49043 Telephone: 616.764.2000 pcQl
ATTACHMENT 1 NUCLEAR MANAGEMENT COMPANY PALISADES NUCLEAR PLANT DOCKET 50-255 May 15, 2003 PALISADES CORE OPERATING LIMITS REPORT Revision 11 Summary of Changes 1 Page Follows
PALISADES CORE OPERATING LIMITS REPORT Revision 11 Summary of Changes Section 1.0 "LCOs" is spelled out as Limiting Conditions for Operation.
The title of section 2.4 is changed to "Total Radial Peaking Factor."
Section 2.1.2 and table are changed to a single shutdown margin (SDM) requirement of 2%. The note below this table is removed.
Section 2.1.2 and Section 2.1.3, the words "ie, non-emergency conditions" are removed.
A note is added to figure 2.2-1 to indicate that a regulating rod is considered fully withdrawn at 2 128 inches.
Below Table 2.3-1, "APL" is spelled out as Allowable Power Level and linear heat generation rate (LHGR) is changed to linear heat rate (LHR). Technical Specifications Basis is added before B 3.2.1.
In section 2.4, the definition of "maximum allowable" is changed to "Peaking Factor Limits."
Table 2.4-1 updates the peaking factor limits for Cycle 17.
Section 3.0 corrects a typographical error cycle's."
ATTACHMENT 2 NUCLEAR MANAGEMENT COMPANY PALISADES PLANT DOCKET 50-255 May 15, 2003 PALISADES CORE OPERATING LIMITS REPORT Revision 11 8 Pages Follow
Procedure No COLR Revision 11 Issued Date 410112003 PALISADES NUCLEAR PLANT TITLE: CORE OPERATING LIMITS REPORT p 1 37
/ R reparerf Date Technical Reviewer
/
Date I /3/A/oi /
0 - o 18 7 PRC Reviewed Date Reference #
Rbact&r Engineering Supervisor Date
Palisades COLR Revision 11 Page 1 of 7 Consumers Energy Company Docket No 50-255 License No DPR-20 Core Operating Limits Report 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:
Title SHUTDOWN MARGIN (SDM)
LCO 3.1.1 3.1.6 3.9.1 Regulating Rod Group Position Limits Linear Heat Rate (LHR)
Total Radial Peaking Factor AXIAL SHAPE INDEX (ASI) 3.1.6 3.2.1 3.2.2
1.0 INTRODUCTION
Section 2.1 2.2 2.3 2.4 I
I 2.5 3.2.4
Palisades COLR Revision 11 Page 2 of 7 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 Tave of 60°F for normal cooldowns and heatups.
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 11 Page 3 of 7 Figure 2.2-1 Regulating Rod Group Position Limits NOTE:
A regulating rod is considered fully withdrawn at 2128 inches.
POWER DEPENDENT INSERTION LIMITS FOUR PUMP OPERATION 100 90 80 70 w
0 0
0 0
20 102_
f il 4
10 132 80 GROUP 4 40 0
132 GROLP2 8
60 132 80 GROUP 3 40 0
CONTROL ROD POSITION (inches withdrawn)
I
Palisades COLR Revision 11 Page 4 of 7 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.
Table 2.3 Linear Heat Rate Limit IE Peak Rod 1
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).
. Unacceptable Operation (0.60, 1.00)
(1.00, 0.93)
- Acceptable Operation 0.4 0.6 0.8 Fraction of Active Fuel Height 1.0 1.2 Figure 2.3 Allowable LHR as a Function of Peak Power Location 2.3
'5 1.2
£1.1 5 11.0 E
-J
,,&20.8 0.7 0.0 0.2 I
I
Total Radial Peaking Factor The radial peaking factor shall not exceed the following:
for P > 0.5 Fr < FS x [1.0+ 0.3 x (1-P)]
and for P < 0.5, Fr < Fr Sx1.15 Where:
=
Measured FrT, FrS
=
Peaking Factor Limits (Table 2.4-1),
P
=
Fraction of rated power.
Table 2.4 Peaking Factor Limits, Frs Reload N All Other Fuel Types (Based on Cycle 17 cycle average burnup) 1.92 2.02 (BOC 17 to 12,000 MWd/MTU) 1.965 (12,000 to 16,020 MWd/MTU)
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.
2.4 Palisades COLR Revision 11 Page 5 of 7 Fr
Palisades COLR Revision 11 Page 6 of 7 TABLE 2.4-2 POWER DISTRIBUTION MEASUREMENT UNCERTAINTY FACTORS AXIAL SHAPE INDEX (ASI)
The ASI limit for the Tiniet function is shown in Figure 2.5-1.
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 2.5 1.2 r 0 j
Unacceptable 1.0 Operation a
0.9 0
0.2 0'6.0.7 Acceptable Operafion r
0.6 0.5 I. 0.4 0.3 0.2
-0.600
-0.400
-0.200 0.000 0.200 0.400 Axial Shape Index Figure 2.5--ASI LIMit for Tinlet Function
Palisades COLR Revision 11 Page 7 of 7 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.