ML20085G532
| ML20085G532 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/13/1995 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20085G520 | List: |
| References | |
| NUDOCS 9506200253 | |
| Download: ML20085G532 (16) | |
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT.
CORE OPERATING LIMITS REPORT 4
Unit 2 - Cycle 17 2
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Note:
This report is not part of the Technical Specifications.
This report is referenced in Technical Specifications.
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9506200253 950613 i
PDR ADOCK 05000282 P
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e PRAIRIE ISLAND NUCLEAR GENERATING PLANT.
CORE OPERATING Liivii!3 REPORT Unit 2 - Cycle 17 Revision 0 4
This report provides the values of the limits for Unit 2 Cycle 17 as required by Technical Specification Section 6.7.A.6.- These values have been established using.
NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met.
Heat Flux Hot Channel Factor Limits Fa"'" = 2.40 K(Z) values are provided in Figure 1.
V(Z) values are provided in Figures 2a through 2e.
Reference Technical Specification Sections: 3.10.8.1 and 3.10.B.2 Nuclear Enthalov Rise Hot Channel Factor Limits Fm "'" = 1.75 PFDH = 0.3 If the nuclear enthalpy rise hot channel factor exceeds its limit in Technical Specification 3.10.B.1, reduce reactor power and the high neutron flux trip setpoint by 3.33% for each percent that the measured nuclear enthalpy rise hot channel factor exceeds the 3.10.B.1 limit.
Reference Technical Specification Sections: 3.10.B.1,3.10.B.2, and 3.10.B.3 j
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cero Operating Limito R port Unit 2, Cycle 17 Revision 0 Linear Heat Generation Rate The 95% probability level ECCS analysis calculation utilized a peak linear heat generation rate of 14.788 kw/ft.
The Appendix K ECCS analysis calculation utilized a peak linear heat generation rate of 15.167 kw/ft for the Fo limit of 2.40.
Reference Technical Specification Section: 3.10.B Axial Flux Difference Limits The Axial Flux difference limits are provided in Figure 3.
The Axial Flux Difference target band is iS%.
Reference Technical Specification Sections: 3.10.B.4 through 3.10.B.9 Shutdown Rod Insedion Limits The shutdown rods shall be fully withdrawn.
Reference Technical Specification Sections: 3.10.D Control Rod Insedion Limits-The control rod banks shall be limited in physical insertion as shown in Figures 4, 5, and 6.
Reference Technical Specification Sections: 3.10.D and 3.10.G Reactor Coolant Flow limit The reactor coolant system flow shall be 2178,000 gpm.
Reference Technical Specification Sections: 3.10.J Page 2 of 15
Cora Oparating Limita Rsport Unit 2, Cycle 17 Revision O Penalty on Fo for Smalli Break LOCA - K(z)
The Small and Large Break LOCA analyses performed for this cycle are valid for Fo s 2.80 and Fo s 2.40, respectively. For this combination of Fa limits for the two LOCA analyses, the Fo limit for the Large Break LOCA analysis is more limiting than the most limiting Fa used in the Small Break LOCA analysis which incorporates the K(z)
Methodology. Therefore, no Fa penalty needs to be applied with respect to the Small Break LOCA analysis. Thus, for the equation in Technical Specification 3.10.B, K(z) is numerically equal to 1. K(z) is shown graphically in Figure 1.
Transient Power Distribution Penalty for Fo - V(z)
The following summarizes the bounding V(z) values for the middle 80% of the core for Prairie Island Unit 2 Cycle 17. The V(z) penalty takes the form of straight lines connecting the data points given for each exposure range and equilibrium Axail Offset (AO) range in Table 1. The V(z) penalty for each exposure range is also shown in Figures 2a through 2e.
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Coro operating Limito Rrport Unit 2, Cycle.17.
. Revision 0 Table 1 Bounding V(z) Values-1 Exposure Range (z, Bounding V(z))'
0 - 2 GWDMtU 0.25,1.125 (Eq AO range: -3% to +8%)
2.75,1.090-5.75,1.090 7.75,1.070 10.25,1.100 11,75,1.100 0 - 6 GWDMTU 0.25,1.125 (Eq A.O range: -6% to +4%).
2.75,1.090 5.75,'1.090 7.25,'1.085 10.25,1.110 4
11.75,1.115 4
0 - 10 GWDMTU 0.25,1.125 (Eq AO range: -6% to +3%)
2.75,1.090 5.75,1.090 7.25,1.085-10.25,1.110
'11.75,1.115-0 - 15 GWDMTU 0.25,1.125
- (Eq AO range:-6% to +2%)
1.75,1.110 2.75,1.090 7.25,1.090 10.25,1.115 11.75,1.115 0 GWD/MTU - End of Cycle 0.25,1.130 (Eq AO range:-6% to +2%)
1.75,1.120 3.25,1.090 5.25,1.105 8.25,1.100 10.25,1.115 11.75,1.120 Note: "z" is the core height in feet Page 4 of 15
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i Caro Operating Limits Report l..
L Unit.2, Cycle-17 l
Revision O-l l
l 1.2 1.1 1.0 0.9 0.8 0.7 K(z)0.6 0.5 0.4 0.3 0.2 0.1 0.0 0
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6 8
10 12 Core Height (ft)
Figure 1 HOT CHANNEL FACTORNORMALIZED OPERATING ENVELOPE -
Page 5 of 15'
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Coro Opertting Limito R5 port Unit 2, Cycle 17 i
Revision o 1.14 0 - 2 GWD/MTU 1.13 Eq AO range:-3% to +8%
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Figure 2a BOUNDING V(Z) VALUES From 0 to 2 GWD/MTU Page 6 of 15
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Caro'Oper; ting Linito Report Unit 2, Cycle 17 Revision 0 1
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1.14 O - 6 GWD/MTU 1.13 Eq AO range:-6% to +4%
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Figure 2b BOUNDING V(Z) VALUES From 0 - 6 GWD/MTU Page 7 of 15
C;ro oper:: ting Limito R: port Unit 2,-Cycle 17 l
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1.13 Eq AO range:-6% to +3%
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Figure 2c BOUNDING V(Z) VALUES From 0 -10 GWD/MTU' Page 8 of 15 -
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.. w c rs operating L12its R; port-Unit 2, cycle.17 Revision O' l
1.14
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1.13 Eq AO range:-6% to +2%
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Figure 2d BOUNDING V(Z) VALUES -
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Coro opercting Limito Report-Unit 2, Cycle 17 Revision 0 1.14 O GWD/MTU - EOC 1.1s Eq AO range:-6% to +2%
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Figure 2e BOUNDING V(Z) VALUES From BOC - EOC Page 10 of 15
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- Cars oper ting Limito Report Unit 2, Cycle 17 Revision O 120 II 110 100 q
l UnacceptaNe UnacceptaNe 90
. Operation Operation
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10 20 30 40 50 60 Deviation From Target Flux Difference Figure 3 DEVIATION FROM TARGET FLUX DIFFERENCE
. AS A FUNCTION OF THERMAL POWER Page 11 of 15
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., s Cors Oper' ting Limits Report Unit 2, cycle 17 Revision O.
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C:r3 Operating'Limito R port Unit 2,' Cycle 17 Revision O j
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Figure 5 INSERTION LIMITS i
100 STEP OVERLAP WITH ONE BOTTOMED ROD (Technical Specification 3.10.G.3) l l
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100 STEP OVERLAP WITH ONE INOPERABLE ROD (Technical Specification 3.10.G.4)
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'l Cor3 operating Limito R port Unit 2, cycle 17
.I Revision 0 l
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. Prepared By-Oley Nelson
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Date PWR Process Manager Fuel Resources Reviewed By:
m fNe== -
~/-W Thomas Breeene Date Superintendent of Nuclear Engineering Prairie Island Reviewed By: Em a b %LL#P, L // /9 C Eugene $ckholt Date Senior Engineer Licensing and Management issues Approved By: / /$?/[0, u/ Mh 6 // /96' Mogsf O Anderson date Director Licensing and Management issues Page 15 of 15