ML20078H332
| ML20078H332 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/10/1994 |
| From: | Breene T, Eckholt E, Nelson O NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20078H325 | List: |
| References | |
| NUDOCS 9411170151 | |
| Download: ML20078H332 (11) | |
Text
{{#Wiki_filter:. _ __ . . PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT Unit 2 - Cycle 16 Revision 1 Note: This report is not part of the Technical Specifications. This report is referenced in Technical Specifications. 4 1 9411170151 941110 PDR ADOCK 05000282 P PDR
f PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT Unit 2 - Cycle 16 Revision 1 This report provides the values of the limits for Unit 2 Cycle 16 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 RTP Fa = 2.40 K(Z) values are provided in Figure 1. V(Z) values are provided in Figure 2. Reference Technical Specification Sections: 3.10.B.1 and 3.10.B.2 No lear Enthalov Rise Hot Channel Factor Limits RTP 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. ; l Reference Technical Specification Sections: 3.10.B.1,3.10.B.2, and 3.10.B.3 !
Core Operating Limits Report Unit 2, Cycle 16 Revision 1 Page 2 of 10 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: 3.10.8 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Specification Sections: 3.10.B.4 through 3.10.B.9 Shutdown Rod insertion Limits The shutdown rods shall be fully withdrawn. Reference Technical Specification Sections: 3.10.D Control Rod lasertion Limits The control rod banks shall be limited in physical insertion as shown in Figures 4,5, and 6. Reference Technical Spec!fication Sections: 3.10.D and 3.10.G Reactor Coolant Flow Lim _ij The reactor coolant system flow shall be 2178,000 gpm. ! Reference Technical Specification Sections: 3.10.J i
l Core Operating Limits Report j Unit 2, Cycle 16 ' Revision 1 ; Page 3 of 10 ! Penalty on Fo for Small 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 Fo limits for the two LOCA analyses, the Fo limit for the Large Break LOCA analysis is more limiting than the most limiting Fo 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 Distrib* ion Penalty for F9- V(z) The following data summarizes the bounding V(z) values for the middle 80% of the core for Prairie Island Unit 2 Cycle 16. The V(z) penalty takes the form of straight lines connecting the data points given for each exposure range in the table below. "z" is the core height in feet. The V(z) penalty for each exposure range is also shown in Figure 2. Exposure Range GWD/MTU (z, Bounding V(z)) 0-2 0,1.140 3,1.085 9,1.085 12,1.115 2 -14 0,1.127 12,1.127 14 -17 0,1.161 12,1.161 17 -19.5 0,1.22G 12,1.220 19.5 - 21.5 0,1.271 12,1.271
Core Operating Limits Report Unit 2, Cycle 16 Revision 1 Page 4 of 10 Prepared By:. h /[ 2-Y y Oley Nelson Date PWR Process Manager Fuel Resources Reviewed By: b u, o m ,, f a Paxx ,
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// 9 9 Eugene Bckh6lt Date Senior Engineer Licensing and Management Issues Reviewed By: < #me #~c //i 7-ff Thomas Breene Date Superintendent of Nuclear Engineering Prairie Island Approved By: 't ? d [4 Sf7R- /E '
3 9#/ Roger /b Anderson D' ate Director Licensing and Management issues
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