NLS2003042, Core Operating Limits Report for Cooper Nuclear Station
| ML031050424 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/04/2003 |
| From: | Coyle M Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NLS2003042 | |
| Download: ML031050424 (23) | |
Text
I Nebraska Public Power District Always there when you need us NLS2003042 April 4, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Core Operating Limits Report Cooper Nuclear Station NRC Docket No. 50-298, DPR-46 The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) the Core Operating Limits Report (COLR) for Cooper Nuclear Station (CNS) for Cycle 22. CNS Technical Specification 5.6.5 requires that core operating limits be documented in the COLR and provided to the NRC upon issuance for each reload cycle for changes to the following cycle specific parameters:
I. The Average Planar Linear Heat Generation Rate (APLHGR)
- 2.
The Minimum Critical Power Ratio (MCPR)
- 3.
The Rod Block Monitor Upscale Allowable Values
- 4.
The power/flow map defining the Stability Exclusion Region For Cycle 22 operations, changes have been made to the operating limits for APLHGR, MCPR, and the power/flow map defining the Stability Exclusion Region. Consequently, the COLR has been updated and it is being submitted as an enclosure. In accordance with 10 CFR 50.4 (b) (1),
we are also transmitting a copy of this COLR to the Regional Office and to the NRC Senior Resident Inspector.
COOPER NUCLEAR STATION P 0 Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811/ Fax: (402) 825-5211 www nppd com
NLS2003042 Page 2 of 2 Should you have any questions regarding this matter, please contact Paul Fleming at (402) 825-2774.
Sincerely, Site Vice President
/cb Enclosure cc:
Regional Administrator w/enclosure USNRC Region IV Senior Project Manager w/enclosure USNRC - NRR Project Directorate IV-I Senior Resident Inspector w/enclosure USNRC NPG Distribution w/o enclosure Records w/enclosure
COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT Cycle 22 Revision 0 Cycle 22, Revision 0
-I-
Signature Page Revision 0 Preparer:
Stephen W. Luther Print Reviewer:
RE Manager:
Sign/Date /
/
/
Paul L. Ballinger Print Sign/DLL Jerry L. Lewis Print Wign!lke Cycle 22, Revision 0
1.0 INTRODUCTION
The Core Operating Limits Report provides the limits for operation of the Cooper Nuclear Station for Cycle 22. It includes the limits for the Rod Block Monitor Upscale Set Point, Average Planar Linear Heat Generation Rate (APLHGR), and Minimum Critical Power Ratio (MCPR). In addition, this COLR also contains:
MCPR limits for an inoperable Main Turbine Bypass System (one bypass valve inoperable)
Power to flow map defining the Stability Exclusion Region Turbine Bypass System response time Maximum allowable LHGR If any of these limits is exceeded, action will be taken as defined in the Technical Specifications.
The core operating limit values have been determined using the NRC-approved methodologies given in References 1, 2, 10, and 11 and have been established such that all applicable plant safety analysis limits are met.
2.0 CORE OPERATING LIMITS Cooper Nuclear Station shall operate within the bounds of the below limits/values. The applicable Technical Specifications are referenced in each subsection.
2.1 Rod Block Monitor Upscale Set Point The Technical Specifications reflect a reference to Allowable Values for the Rod Block Monitor (RBM) upscale (power referenced) trip level setting, found in Reference 9, are as follows:
Lowest Rated Low Trip Set Intermed Trip Set High Trip Set MCPR Limit Point (LTSP)
Point (ITSP)
Point (HTSP)
(LPSP*P*IPSP)
(IPSP<P*HPSP)
(HPSP<P) 21.20
<114.0/125
<108.5/125
<104.5/125
Ž1.25
- 117.0/125
- 112.5/125
- 107.5/125 21.30
- 120.0/125
- 115.0/125
- 110.5/125 LPSP, IPSP, and HPSP are the Low Power Set Point, Intermediate Power Set Point, and High Power Set Point, respectively.
The trip level settings associated with this MCPR limit have been generically calculated and verified to bound the Rod Withdrawal Error Analysis for Cycle 22 operation.
Technical Specification
Reference:
3.3.2.1 Cycle 22, Revision 0 2.2 Average Planar Linear Heat Generation Limits The most limiting lattice APLHGR value (excluding natural uranium) for each fuel bundle as a function of Planar Average Exposure, core power, and core flow is calculated by multiplying the value from Figures 1, 2, 3, 4, 5, and 6 by the smaller of the MAPLHGR Flow Factor, MAPFACF (Figure 7) or the Power-Dependent MAPLHGR Factor, MAPFACp, (Figure 8). APLHGR values determined with the SAFER/GESTR-LOCA methodology are given in References 2, 3, and 5 while MAPFACF and MAPFACp were determined in Reference 8.
The calculated maximum APLHGR (MAPLHGR) limits in Figures 1, 2, 3, 4, 5 and 6 are conservative values bounding all fuel lattice types (excluding natural uranium) in a given fuel bundle design. MAPLHGR limits for each individual fuel lattice design in a bundle design, as a function of axial location and average planar exposure, are determined based on the approved methodology referenced in Technical Specification 5.6.5 and loaded in the process computer for use in core monitoring calculations. The MAPLHGR values for these lattices, along with the axial location of each lattice in the bundle, are considered proprietary information by General Electric and are given in Reference 3 as a function of planar average exposure.
The MAPLHGR limits referred to above are for two recirculation loop operations.
For single loop operation, the limiting APLHGR value is multiplied by 0.77 for GE8x8 NB fuel (as can be found in Reference 5) and by 0.91 for GE14 fuel (as can be found in Reference 5).
Technical Specification
Reference:
3.2.1 and 3.4.1 2.3 Linear Heat Generation Rate Limit The limiting power density and maximum allowable Linear Heat Generation Rate (LHGR) referred to in Technical Requirements Manual Section T 3.2.1 is the design LHGR. The design LHGR for fuel type GE 8x8 NB is 14.4 kW/ft as found in Reference 12. The design LHGR for fuel type GE14 is 13.4 kW/ft as found in Reference 13.
2.4 Minimum Critical Power Ratio Limits The operating limit MCPR (OLMCPR) values are a function of core thermal power, core flow, fuel bundle, scram time (r), and fuel exposure. The scram time (T) is determined from CNS Procedure 10.9, Control Rod Scram Time Evaluation.
The OLMCPR values are as follows:
For core thermal power > 25 percent and <30 percent of rated power, the OLMCPR is the power dependent MCPR (MCPRp) from Figure 9.
Cycle 22, Revision 0 For core thermal power 2 30 percent of rated power, the OLMCPR is the greater of either:
The applicable flow dependent MCPR (MCPRF) determined from Figure 10, or the appropriate scram time (T) dependent MCPR at rated power from Figures 11, and 12, multiplied by the applicable power dependent MCPR multiplier (Kp) from Figure 9.
The appropriate scram time (X) dependent MCPR at rated power with One Turbine Bypass Valve Unavailable is shown in Figure 13.
The system response time for the Turbine Bypass System to be at 80% of rated bypass flow is 0.3 seconds.
For single recirculation loop operation, the OLMCPR is 0.02 greater than the two recirculation loop operation OLMCPR.
Technical Specification
References:
3.2.2, 3.4.1 and 3.7.7 2.5 Power/Flow Map The power/flow map defining the Stability Exclusion Region can be found as Figure 18. References 5 and 6 reflect the documents describing the current Cooper Nuclear Station power/flow map. The Stability Exclusion Region boundary is given by the equation I 2 W-)VW
( W-JWB
- where, P = a core thermal power value on the region boundary (% of rated),
W = the core flow rate corresponding to power, P, on the region boundary (% of rated),
PA = core thermal power at point A (% of rated),
PB = core thermal power at point B (% of rated),
WA = core flow rate at point A (% of rated), and WB = core flow rate at point B (% of rated).
Technical Specification
Reference:
3.4.1 Cycle 22, Revision 0
3.0 REFERENCES
- 1.
NEDE-2401 I-P-A-14-US, June 2000, General Electric Standard Applicationfor Reactor Fuel.
- 2.
NEDC-32687P, Revision 1, March 1997, Cooper Nuclear Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis.
- 3.
Lattice Dependent MAPLHGR Report for Cooper Nuclear Station Reload 21, Cycle 22, 0000-0002-9865-MAPL, Revision 0.
- 4.
Letter (with attachment), R.H. Buckholz (GE) to P.S. Check (NRC) dated September 5, 1980, Response to NRC Request for Information on ODYN Computer Model.
- 5.
Supplemental Reload Licensing Report for Cooper Nuclear Station Reload 21, Cycle 22, 0000-0002-9865-SRLR, Revision 0.
- 6.
GE-NE-A 13-00395-01, Class 1, November, 1996, Application of the "Regional Exclusion with Flow-BiasedAPRMNeutron Flux Scram" Stability Solution (Option l-D) to the Cooper Nuclear Station, Licensing Topical Report.
- 7.
Letter from James R. Hall (NRC) to G. R. Horn (NPPD) dated September 23, 1997, Approval of SAFER/GESTAR LOCA Analysis for Cooper Nuclear Station (TAC NO. M98293)
- 8.
GE-NE-L12-00867-12, Cooper Nuclear Station MIG Project Task 900: Transient Analysis, Revision 1, May 2000.
- 9.
NEDC 98-024, Revision 3, May 2000, APRM-RBMSetpoint Calculation
- 10.
NEDO-3 1960-A and NEDO-3 1960-A Supplement 1, BWYR Owner's Group Long-Term Stability Solutions Licensing Methodology.
(The approved revision at the time the reload analysis is performed.)
- 11.
NEDE-23785-1 -P-A, The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume III, Revision ], October 1984.
- 12.
Nuclear Design Report for Cooper Nuclear Station Reload, 18, J 11-03354-03, July 1998.
- 13.
GE-NE-L 12-00867-09-02, Cooper Nuclear Station MIG Project Task 407: SAFER/GESTR-LOCA Analysis, May 2000.
- 14.
Letter from S. Shelton (GNF) to J.L. Lewis (NPPD) dated December 21, 2000, GE9B LHGR Relaxation for Cooper Nuclear Station
- 15.
NEDE-31152P, GE Fuel Bundle Designs, December 1988 (As Revised)
- 16.
NEDC-32538P-A, Determination ofLimiting Cold Water Event
- 17.
GE-NE-JI 103910-09-02P, Cooper Nuclear Station ECCS-LOCA Evaluation for Cycle 21, August 2001.
- 18.
GE-NE-J1 103910-09-01, Cooper Nuclear Station ECCS-LOCA Evaluationfor GEI4, August 2001.
- 19.
NEDC-32687P, Cooper Nuclear Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis, Revison 1, March 1997.
Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure I Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2610, 3.93 w/o with 17GZ GE14C Fuel 15 00 1 12.00 9.00 i,
=
600
-ja-<
300 0.00 0.00 10.00 20 00 30.00 40 00 50.00 60.00 70.00 Planar Average Exposure (GWdIST)
DATA COORDINATES (Reference 3)
PlanarAverage Exposure (GWD/ST) 000 020 1 00 200 3 00 400 500 600 700 800 900 1000 11 00 1200 1300 1400 1500 17 00 20 00 25 00 3000 3500 4000 4500 5000 55 00 57 05 57.08 57.41 57.42 MAPLHGR (kW/ft) 934 9.43 9.58 9.79 1000 10.23 1045 10 61 1074 1088 11 01 1113 11.23 1132 1139 11.41 1142 11.24 1092 1039 9.86 9.37 8 87 8 35 7.82 5.86 484 483 488 4 87 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2568, 3.98 wlo with 16GZ GE14C Fuel 15.00 g
12.00 9.00
=
6 00
-j0E 4
3 00 I
4
.I 000 0.00 10.00 20.00 30 00 40.00 50.00 60 00 Planar Average Exposure (GWd/ST)
DATA COORDINATES (Reference 3)
Planar Average Exposure (GWDIST) 000 020 1.00 2.00 3.00 4 00 5.00 600 7.00 8.00 9.00 10.00 11.00 1200 1300 1400 1500 1700 2000 2500 30 00 35.00 40.00 45.00 5000 55 00 57 47 57.49 5831 58.32 MAPLHGR (kW/fR) 9.63 9.64 9.71 986 1003 1023 1045 10 66 1087 I1 09 11.20 1128 1136 1142 11.42 11 42 11 42 11 33 I1 00 1043 989 939 890 838 7 85 607 4 83 4 83 4 89 4 88 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2472, 3.79 w/o with 17GZ GEi4C Fuel 15.00
`
12.00 9S 9.00
=
6.00
-E a-<' 3.00 0.00 0 00 10.00 20.00 30 00 40 00 50.00 60.00 Planar Average Exposure (GWd/ST)
DATA COORDINATES Reference 3)
Planar Average Exmosure (GWD/ST) 000 020 1 00 2.00 3.00 4 00 5.00 600 7.00 8 00 9 00 10 00 11 00 1200 1300 1400 1500 1700 2000 2500 30.00 3500 4000 45 00 5000 5500 5621 56.48 56 83 56.90 MAPLHGR (kW/ft) 925 932 9.45 962 980 999 10 18 10 38 1052 1062 1074 1086 1096 11 04 1110 1113 11 04 1085 1056 1010 967 925 8 81 831 775 5 52 4 91 493 4.83 483 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2380, 3.85 wlo with 14GZ GE14B Fuel 0
-ja.
15.00 -_
12.00 -_
9.00 4 6.00 3.00 0.00 -
0.00 pp Ii 10.00 20.00 30.00 40.00 50.00 60.00 Planar Average Exposure (GWd/ST)
DATA COORDINATES (Reference 3)
Planar Average Exposure (GWD/ST) 000 020 1 00 2 00 300 4 00 500 600 700 800 900 1000 11 00 1200 1300 1400 1500 17.00 20 00 25 00 3000 35.00 40.00 45.00 50.00 5500 56 86 56.91 57.87 57.93 MAPLHGR (kW/ft) 902 911 926 949 971 992 10.05 10.16 1024 10.31 10 38 1046 1054 1063 1074 10 83 1080 1069 1046 1005 964 919 869 814 751 685 6 59 659 663 6 65 Cycle 22, Revision 0
-.10-
CORE OPERATING LIMITS REPORT Figure 5 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2299, 3.50 w/o with I0GZ1 GE8X8NB Fuel 15.00 8 12.00 9.00 I
6.00
- 0.
3.00 E
0.00 a
.I 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Planar Average Exposure (GWd/ST)
DATA COORDINATES (Reference 3)
Planar Average Exposure (GWD/ST) 000 020 1.00 2 00 300 4.00 5 00 600 700 800 900 1000 1250 1500 2000 25 00 3500 4500 5392 5400 MAPLHGR (kW/ft) 1159 11 63 1171 11 84 1199 12 14 1226 12 39 1253 1266 12.81 1285 1279 12 51 11 78 11 08 1053 951 5 74 5 75 Cycle 22, Revision 0
-I -
CORE OPERATING LIMITS REPORT Figure 6 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2205, 3.50 wlo with IOGZ GE8X8NB Fuel 4 C Afn I
-j0M
-I U.UU -
12.00 6.00 -
3.00 0.00 0.c A,
^*-
+
+
1o I
I 10.00 20.00 30.00 40.00 50.00 60.00 Planar Average Exposure (GWdIST)
DATA COORDINATES (Reference 3)
Planar Average Exosure (GWDIST) 0 00 0.20 1 00 200 3 00 4 00 5 00 600 700 8 00 9 00 1000 1250 1500 2000 2500 3500 4500 5400 5402 MAPLHGR (kW/ft) 11.59 11.63 11.71 11.85 12.00 12.13 12.26 12.38 12.52 12.65 12.80 12.84 12.81 12.52 11.78 11.09 10.53 954 5 75 5 74 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 7 Reference 8 Figure 3-11 Cooper Nuclear Station ndent MAPLHGR Factor, l' 1.1 1
0.9 08 ML U-a.m 0.7 06 05 04 03 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)
Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 8 Reference 8 Figure 3-9 Cooper Nuclear Station Power-Dependent MAPLHGR Factor MAPFAC(p) 1.00 0.90 0 80 0.70 0.60 a-0~
LL 0.50 0 40 0 30 020 tp)=
MAPFACp)
MALHGRstd MPLHGRstd = Standard MAFPLHGR Lints For P<25%- No Thermal Lints rAonitoring Required No fimts s pecif ied For 25% < P < 30%
MAPFAC(p)=0 53 + 0.005(RL30%)for Flow < 50%
MAPFAC(p)=0 49 + 0.005(P-30%)for Flow > 50%
< 50% Fo For 30% < P MAPFAC(p) = 1 0 + 0.005224(P-100%)
0 10 20 30 40 50 60 70 80 90 100 POWER (% Rated)
Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 9 Reference 5 Cooper Nuclear Station Power-Dependent MCPR Limits, Kp and MCPRp 4.0 3.5 3.0 L 2.5 2.0 1.5 1.0 IIIIIIIIIaIIIII low > 500/c I
Operating Limit MCPR (P) = Kp ' Operating Limit MCPR (100)
For P< 25%- No Thermal Limits Monitoring Required No limits specified For 25% < P < P(Bypass) (P(Bypass) = 30%)
K(P) = [K(Byp) + 0 0500(30% - P)] / OLMCPR(100)
K(Byp) = 2.24 for Flow < 50%
K(P) = [ K(Byp) + 0 0519(30% - P)] I OLMCPR(100)
K(Byp) = 2 66 for Flow > 50%
For 30% < P < 45%: K(P) = 1 28 + 0 0134 (45% - P)
For 45% <P <60% K(P)= 1.15+000867(60% - P)
For 60% <P.
K(P) = 1 0 + 0 00375 (100% - P)
IIaIIIIIII 200 I -
I -
I I
Flow <= 50%
IIIIII I
I I
I I
I I
II 20 30 40 50 60 70 Power (% rated)
Cycle 22, Revision 0 80 90 100 110
CORE OPERATING LIMITS REPORT Figure 10 Reference 5 Cooper Nuclear Station Flow-Dependent MCPR Limits, MCPR(Q) 1.8 1.7 -
1 6 1.5 I
I I
I I
GEXL05 'orrectiorj 117.0%
112.0% \\
107.0%1R For W(C) (% Rated Core Flow) > 40%
MCPR(F) = MAX(1.22, A(F) - W(C) /100 + B(F))
Max Flow = 117 0 A(F) = -0 644 B(F) = 1 843 Max Flow =1120 A(F) = -0613 B(F) 1.780 Max Flow = 107.0 A(F) = -0 597 B(F) = 1.729 Max Flow = 102 5 A(F) = -0 582 B(F) = 1 686
= GE14 < 40% Flow For W(C) (% Rated Core Flow) < 40% For GEXL05 only MCPR(F) = (A(F)' W(C) /100 + B(F))' (1 + 0 0032 ' (40 - W(C)))
102.5%
w K
i a-U
'1 er GEXL z
'N\\
\\
S1
I s
All OtU 1.4 1 3 F
- 4.
_ __I I_ 1 _
_ 1
_ 4_
N I
\\K\\11 1 2 I
I I
I -
4
+
1.1 I
I i
20 30 40 90 100 110 50 60 70 80 Core Flow (% Rated) 120 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure I I Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), All Fuel 1.47 -_
1.46 -_
1.45 -_
1.44 -_
1.43 -_
t 1.42 --
0 1.41 -_
1.4 -_
1.39 -
1.38 1.37 -
1.36 -
0.0 0.1 0.2 0.3 0.4 0.5 0 6 0.7 0.8 0.9 1.0 Tau Exposure Range BOC22 to EOC22-2315 MWd/MT (2100 MWd/ST) ICF Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 12 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), All Fuel a-C.
1.59 1.58 1.57 -
1.56 -
1.55 _
1.54 --
1.53 -
1.52 -
1.51 1.5 -
1.49 -
1.48 -
1.47 1.46-1.45 1.44 _
1.43 1.42 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0 8 0.9 1.0 Tau Exposure Range: EOC22-2315 MWd/MT (2100 MWd/ST) to EOC22 ICF Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 13 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), All Fuel 1.59 1.58 1.57 1.56 1.55 1.54 1.53 a
1.52 IL 1.51 1.5 5 1.49 1.48 1.47 1.46 1.45 1.44 1.43 1.42 0 0 0.1 0.2 0.3 0.4 0.5 0 6 0.7 0.8 0.9 1.0 Tau Exposure Range BOC22 to EOC22 ICF_1TBPOOS Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 14 Cycle 22 Stability Exclusion Region 110 000 100 000 90 000 X
80 000 Point A 70 000 -
60.000 -
50 000 -
40000 -
Point B 30 000 -
20 000 -
0 3
40 50 60 70 80 Core Flow (%)
Exclusion Region Endpoints A
B Power (% rated) 77.1 36.8 Flow (% rated) 49.7 32.5 Cycle 22, Revision 0 I
ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS Correspondence Number: NLS2003042 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE None 4-4-
4-1-
4-4-
PROCEDURE 0.42 l
REVISION 12 l
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