ML20126G596

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Rev 0 to Prairie Island Nuclear Generating Plant COLR Unit 1 - Cycle 16
ML20126G596
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 12/30/1992
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20126G595 List:
References
NUDOCS 9301040154
Download: ML20126G596 (10)
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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 ADOCK'0500g2 . DR 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 2.45 Fq ~ 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 T ~ + .s. s..

i'l 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 Axini Flux Difference Limits i 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Specification Sections: 3.10,B.4 through 3.10.B 9 1 Shutdown Rod insertion 1.imits The shutdown rods shall be fully withdrawn.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-The reactor coolant system flow'shall be a: 178,000 gpra. i- - Reference Technical 5,.ecification Section: 3.10.J i'_ P W l : r. f O o 't "AT' ft ar s 44 c.<r 7+-g e 5, w y IF re-7*y-t 53 N h gJJWEE. :5 ddy'--oc ~ 4

.m___ F Cot e 4erstitig 1.tn.its koport Unit 1, Cycle 16 4 Revision 0 Page 3 of 9 Prepared By: rpg ;p f5 IL/~L*L [1z_ g. Eugene ekholt Dato Reviewed By:_ 4' g /fsgf,4 d /;)4dge-e - j s ir 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 /hAI 7 2-.-- i mas M Parker / Dat Director Nuclear Licensing .. =.. = 97 7 r'

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