ML042400106
| ML042400106 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/24/2004 |
| From: | Domonique Malone Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| COLR, Rev 12 | |
| Download: ML042400106 (11) | |
Text
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Committed to Ncerxel Palisades Nuclear Plant Operated by Nuclear Management Company, LLC August 24, 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 ODerating Limits ReDort - Revision 12 Nuclear Management Company, LLC is providing revision 12 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 12 of the COLR.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
/J 4114 N
O r
Daniel J. Malone Site Vice-President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosures (2) cc: Administrator, Region IlIl, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 27780 Blue Star Memorial Highway
- Covert, Michigan 49043-9530 Telephone: 269.764.2000 4 oo1l
ENCLOSURE 1 PALISADES CORE OPERATING LIMITS REPORT REVISION 12
SUMMARY
OF CHANGES Nuclear Management Company, LLC submitted a license amendment request (LAR) on September 18, 2003 for relocation of the departure from nucleate boiling (DNB) limits in Limiting Condition for Operation (LCO) 3.4.1 of Technical Specifications to the Core Operating Limits Report (COLR). On August 2, 2004, the Nuclear Regulatory Commission approved this LAR via amendment 217.
This COLR revision implements changes made by amendment 217.
In addition, an editorial change is made to add Nuclear Management Company, LLC to the title.
Page 1 of 1
ENCLOSURE 2 PALISADES CORE OPERATING LIMITS REPORT Revision 12 8 Pages Follow
Procedure No COLR Revision 12 Issued Date 8/24/04 PALISADES NUCLEAR PLANT TITLE: CORE OPERATING LIMITS REPORT 92, e
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7/ ?A A
l41 Preparer ('
ate Technical Reviewer Date S/-7 c!/o' 0se 0
-7 78 PRC Reviewed Date Reference #
Reactor Engineering Supervisor Date
Palisades COLR Revision 12 Page I of 7 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 12 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 Ž22% 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 600F 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 12 Page 3 of 7 POWER DEPENDENT INSERTION LIMITS FOUR PUMP OPERATON 100 70
~40 30 16 l E11J201 10L5Th RTINGNEGION_
10-IN I
I 132 80 GROLP4 40 0
132 GROUP2 80 60 132 80 GROUP3 40 0
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.
2.3 Palisades COLR Revision 12 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 =
FA(Z) =
Maximum allowable LHR shown in Table 2.3-1.
Allowable LHR as a function of peak power location shown in Figure 2.3-1.
Table 2.3 Linear Heat Rate Limit II 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).
1.2 IX1.1 3i oWE 30 I S O0.9 20.8
.11
. Unacceptable Operation (0.60, 1.00)
(1.00, 0.93)
- Acceptable Operation 0.7 0.0 0.2 0.4 0.6 0.8 Fraction of Active Fue I He Ight 1.0 1.2 Figure 2.3 Allowable LHR as a Function of Peak Power Location
(,
Palisades COLR Revision 12 Page 5 of 7 2.4 Total Radial Peaking Factor The radial peaking factor shall not exceed the following:
for P > 0.5 F. < FTSrx[1.0+0.3x(1-P)]
Fr < FrTsx1.15 and for P < 0.5, Where:
=
Measured F T TS 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.
Palisades COLR Revision 12 Page 6 of 7 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 1.0 Unacceptable 1.1 Opration X0.9 0.8 0.7 Acceptable a0.6 Operation 0
'- 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 Q
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
Palisades COLR Revision 12 Page 7 of 7 2.6 PCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
Limits
- a.
Pressurizer pressure 2 2010 psia and < 2100 psia;
- b.
The PCS cold leg temperature (Ta) shall not exceed the value given by the following equation:
Tc < 542.99 + 0.0580(P-2060) + 0.00001(P-2060)2 +
1.125(W-1 38) - 0.0205(W-138)2 Where:
Tc
= PCS cold leg temperature in OF P
= nominal operation pressure in psia W
= total recirculating mass flow in I E6 lb/hr corrected to the operating temperature conditions.
NOTE:
If the measured primary coolant system flow is greater than 150.0 E6 Ibm/hr, the maximum Tc shall be less than or equal to the Tc derived at 150.0 E6 Ibm/hr.
- c.
PCS total flow rate > 352,000 gpm.
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.