ML20058L108
ML20058L108 | |
Person / Time | |
---|---|
Site: | Prairie Island ![]() |
Issue date: | 07/27/1990 |
From: | Parker T NORTHERN STATES POWER CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
References | |
NUDOCS 9008060273 | |
Download: ML20058L108 (19) | |
Text
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i'l f I Northern States Power Company 414 Nicollet Mall Minneapolis. Minnesota $54011927 Telephone (612) 330 5500 July 27, 1990 Tech. Spec. 6.7.A.6 1 Director of Nuclear Reactor Regulation ; U S Nuc1 car Regulatory Commission Atta: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PIANT , Docket Nos. 50-282 License Nos. DPR-42 , I e Revision 1 to the Core Operating Limits Report for Unit 1 Cvele 14 ' The attached revision to the Core Operating Limits Report for Prairie Island Unit 1 Cycle 14 is being provided in accordance with the requirements of Technical Specification Section 6.7.A.6. The' limits specified in the-attached Co're Operating Limits Report have been established using NRC' approved methodology. Please contact us if you have any questions related to this report. Thomas M Parker ' Manager Nuclear Support Services c: Regional Administrator - Region III, NRC NRR Project Manager, NRC , Senior Resident Inspector, NRC MPCA !
- Attn: J W Ferman C Charnoff .
Attachment:
Core Operating Limits Report Unit 1 Cycle 14, Revision 1
? n r) 9008060273 900727 I
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i ( PRAIRIE ISLAND NUCLEAR GlINERATING PLANT I 1 CORE OPERATING LINITS REPORT Unit 1 - Cycle 14 Revision 1 b i I l
- )
i
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., "*:-'* *: ;p-l " tl } W . PRAIRIE, ISLAND NUCLEAR GENERATING PLANT -
j ^l CORE OPERATING LIMITS REPORT- [ Unit 1 Cycle 14 ; i Revisioni1 l j6, 4 This report provides the values of,the limits for. Unit 1 Cycle 14 as required i
'by Technical Specification Section 6.7,A.6. -These values have been- - established using:NRC approved methodology and are established such that all j applicable-limits of the plant safety analysis are met, t . Heat Flux Hot Channel Factor Limits RTP !
Fa - 2.50.
'K(Z). values are provided in Figure 1. -[
f V(Z) values are provided in Figures 2a through 21 . . Reference Technical Specification Sections: 3.10.B.1-and 3.10 B.2 7 Nuclear Enthalov Rise Hot Channel Factor Limita + RTP' F.tV P 3g -11.70 ;
~ . PFDH. ,0.3 > Mi . ' 7' " - If the nuclear enthalpy rise hot channel factor exceeds-its limit in Technical i . Specification 3.10 B.1, reduce the high neutron-flux. trip setpoint by 3.33% .for each percent' that the measured nuclear enthalpy rise hot channel factor ~ !9 iexceeds the 3.10 B.1 limit. .; ,1 4 '
Reference Technical Specification Sections: 3.10.B.1, 3.10.B.2 and 3.10.B 3 m
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% p: (' i e tor] operatine Ll lts Report-Wit 1, en te 14 Revision 1
{p PMp 2 of 17 ;) h 51
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b Linear llear Generction Rate - l
!The 95% probability level ECCS analysis calculation utilized a peak linear. '
t
. heat generation rate'of 14.2 kw/ft.
The Appendix K ECCS analysis calculation utilized'a peak linear heat
. generation rate _ of 15.8- kw/f t for the F, limit of 2.5.
Reference Technical Specification Section: 3.10.B h r Axial Flux Difference Limits ') u L,
-+
The' axial flux difference limits are provided in Figure 3.
, -The Axial Flux Difference target band is iSt.
i
^
Reference Technical Specification _ Sections: 3.10 B.4 through 3.10.B'.9 J
~ Shutdown Rod Insertion Limits .l The shutdown rods'shall be fully withdrawn. ,
T Reference Technical Specification Section: 3.10.D ; 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 Section: 3.10 D i Reactor Coolant Flow Limit i The reactor-coolant system flow shall be a 178,000 gpm.
Reference Technical Specification Section: 3.10.J L o-i
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. - + . Core Operating Ll;its Report Unit 1, Cycle 14 Revision 1 , Page 3 of 17 Prepared By: _ hS9 _ 7 N? 90 EugeneWckholt ' D4te Reviewed By: b 7pm Orcrac. 7[2 7,!*o Thomas Breene" F Date i Superintendent of Nuclear Engineering .j Prairie Island i Reviewed By: hc . C.4 /V '-
J eff Rbger Anderson Manager & / date / { Nuclear Analysis .'
/ / !'
Approved By: , M 7/ M7 [O Thomas M Parker ' 'Date' Manager Nuclear Support Services , i s i
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. . Core Operating Limits Rtport Unit 1, Cycle 14 Revision 1 Page 4 of 17 i
1.2 1 (6.0.1.0) '
, 1.0 ,
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6 8- 10 12 Core Height (ft) , Figure 1 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE t
i CIre Operating L12lts Report ; Unit 1, Cycle 14
- i Revision i Page 5 of 17
'~
Figure 2a .
.V(Z) AS A FUNCTION OF CORE HEIGHT '
UNIT 1 CYCLE 14 (5,000 MWD /MTU) v(z) penalty 1.14 1.13 I 1.12 I i 1.11 h 1.1 t . 1.09 1.08 ! , - 7 i l l 1.07 1 i I f y " ! F - 1.06
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( LINEAR INTERPOLATE BETWEliN AXI AL i- HEIGHT AND EXPOSURE STEPS i l l l
s ,
. C:re Operating LI:lts Report Unit 1, Cycle 14 Revision i Pope 6 of 17 i
Figure 2b ' i V(Z) AS A FUNCTION OF CORE HEIGHT UNIT 1 CYCLE 14 (6,000 MWD /MTU) I v(z) penalty 1,14 . , , , 1 l l i l l , I :
- 1,13 - 4 - ' + l- +
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1.02 i 0 1 2 3 4 5 6 7 8 9 10 11 12 13 axial height, feet i 1 LINEAR INTERPOLATE BETWEEN AXIAL
' HEIGHT AND EXPOSURE STEPS l 1
l l l
. . C:re Operating Limits Report Unit 1, Cycle 14 Revision 1 Page 7 of 17 Figure 2c . V(Z) AS A FUNCTION OF CORE HEIGHT UNIT 1 CYCLE 14 (7,000 MWD /MTU) v(z) penalty
- 1.14 - i i ,
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1.02 0 1 2 3 4 5 6 7 8 9 10 11 12- 13 axial height, feet LINEAR INTERPOLATE BETWEEN AX1 AL HEIGHT AND EXPOSURE STEPS
i
. s . 03re Oper tin 0 L121ta Report . Unit 1, CycIe in Revision i Pope 8 of 17 Figure 2d '
V(Z) AS A FUNCTION .OF CORE HEIGHT UNIT 1 CYCLE 14 (8,000 MWD /MTU) v(z) penalty 1.14 , , ,
- : ; i ,, l l !
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r.- T V-. q
- Cire Operating Linits Report
. Unit 1, Cycle 14 Revision 1 ,
Page 9 of 17
]
Finure 2e l V(Z) AS A FUNCflON..OF CORE HEIGHT !
. UNIT 1 CYCLE 14 (10,000 MWD /MTU) I l
v(z) penalty ; 1.14 1.13 *- 1.12 j i i i i t i 1 i ' 1.11 -
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-HEIGHT AND EXPOSURE STEPS
C re Operating Ll2fts Report Unit 1, CycIe 14 Revision 1 Page 10 of 17 Figure 2f V(Z) AS A FUNCTION OF' CORE HEIGHT UNIT 1 CYCLE 14 (12,000 MWD /MTU) v(z) penalty 1.14 1.13 t 1.12 i i
.l .1 1 -
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-1 -
Cire Operating Ll;lts Report Unit 1, Cycle 14 Revision 1 Page 11 of 17
- Figure 2 ;
' V(Z) ASLA FUNCTION g0F . CORE HEIGHT UNIT 1 CYCLE 14 (13,000 MWD /MTU) ;
v(z) penalty 1.14 i , 1.13 } t l
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$ Ccro Operatine Li%lta Report
- Unit 1, Cycle la kevision i Page 12 of 17 Figure 2h V(Z) AS: A FUNCTION OF CORE HEIGHT UNIT 1 CYCLE 14 (15,000 MWD /MTU)'
v(z) penalty 1.18 , ,
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.. 1 .. Ctre Operating Lizits R: port j Un't 1, Cycle 14 I Re..sion 1 i Page 13 of 17 l
Fi l V(Z) AS A FUNC'gure ION 2i OF CORE HEIGHT 1 UNIT 1 CYCLE 14 (17,000 MWD /MTU) l v(z) penalty i 1.24 , l i I t 1'
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C*re Operating . tits Report Unit 1, Cycle 14 Revision 1 i Pope 14 of 17
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Core Opercting Linita Report unit 1. Cycle 15 Revision 1 Page 15 of 17 t 0: *
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