ML20126G596
| ML20126G596 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/30/1992 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20126G595 | List: |
| References | |
| NUDOCS 9301040154 | |
| Download: ML20126G596 (10) | |
Text
{{#Wiki_filter:7 g. i PRAIRIE ISLAND NUCLEAR GENERATING PLANT ' CORE OPERATING LIMITS REPORT Unit 1 - Cycle 16 i Revision 0 Note: This report is not part of the Technical Specifications. This report is referenced in Technical Specifications, 9301040154 921230
. DR ADOCK'0500g2 J
s PRAIRIE ISIMID HUCLEAR CENERATING PIANT l CORE OPERATING LIMITS REPORT , Unit 1 Cycle 16 Revision 0 This report provides the values of the limits for Unit'l 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 inet, llent Flux flot Channel Factor tirnits i kTP Fq ~ 2.45 K(2) 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 4 Hucicir Enthalov Rise llot Channel- Factor Limits
~
. RTP {
F an' - 1. 70 ; PPDil - 0.3 4 If the nuclear enthalpy rise hot channel factor exceeds its liinit .in Technical' > Specification 3.10.B.1, : reduce the high neutron-l flux trip netpoint by L ?*1 for each percent that the measured nuclear.enthalpy rise hot channel factor exceeds the 3.10.B.1 limit. ; Reference Technical Speci fication Sections: 3.10.B.1, 3 10.B.2 and 3.10.B;3 ., E
. f i
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- Core opeseting 1.imits kegmet.
. 11ni t.14 Cycle 16 mevision o Fase 2 of 9 Linear Heat Generation Rate The 954 probability level ECCS analysis calculation utilized a peak linear ;
- heat generation rate of 14.2 kw/ft. !
The Appendix K ECCS analysis calculation utilized a peak linear heat ! generation rate of 15.5 kw/ft for the Fn limit of 2.45. Reference Technical Specification Section: 3.10.B .l 1 i Axini Flux Difference Limits The axial flux difference limits are provided in Figure 3. The Axial Flux Difference target band is 154. . Reference Technical Specification Sections: 3.10,B.4 through 3.10.B 9 1 Shutdown Rod insertion 1.imits The shutdown rods shall be fully withdrawn. Reference Technical Specification Section: 3.10.D i Control Rod Insertion 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 3.104G' Renctor Coplant._, Flow IJmit-i- The reactor coolant system flow'shall be a: 178,000 gpra.
- Reference Technical 5,.ecification Section: 3.10.J i'_
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- Unit 1, Cycle 16 4
Revision 0 Page 3 of 9 Prepared By: g. rpg ;p f5 IL/~L*L [1z_ Eugene ekholt Dato s ir Reviewed By:_ 4' g /fsgf ,4 d /;)4dge-e - j - 2$ */M __, Thornas Breene Date Superintendent of Nuclear Engineering Prairic Isl.and f) /l Reviewed by: !6 #7t _ '.W' ?o% ///9 7, 9,A Rdgef' Anderson / D4/to Director Nuclear aly a Apprwed By:_ [M i mas M Parker
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/ Dat Director Nuclear Licensing
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Co.o Operatisig Limits Repost Unit 1, Cycle 16 Revision 0 l Fase 4 of 9 1.2 (6.0,1.0) l (12.0.0 92:1 l 1.0 '
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- l Extiosure Rnnt.g Itoundinn V(z) Value-O to 2,000 MWD /MTU 1.120 2,000 to 14,000 MWD /MTU 1.135 14,000 to 17,500 MWD /HTU 1.200 i
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