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Category:FUEL CYCLE RELOAD REPORTS
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[Table view]
Category:TEXT-SAFETY REPORT
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ML20151Z9651998-08-31031 August 1998
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ML20238F6551998-08-28028 August 1998
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1999-09-30
[Table view] |
Text
. --
MTAttiMBL2 ,
M2C_4_CorJL0p enting_ LinLtLEesort w
i 9205040128 920427 PDR ADOCK-05000455 l p PDR ZNLD/1764/5 2
_ _ _ - _ - _ _ _ _ - _ _ - _ _ _ - - _ . _ - _ _ .i
Byron Unit 2 Cycle 4 Operating Limit Report - Fxy Portion This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of ine Byron Unit 2 Nuclear Plant Technical Specifications. 1 The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 4 shall be:
- a. For the lower core region from greater than or equal to 0% to less than or equal to 50'/.:
- 1. For all core planes containing bank "D" control rods:
RTP F
xy 1 1.990, for Bu 1 8000 MHD/MTU ,,
1 1.990, for Bu > 8000 MHD/MTV
- 2. For all unrodded core planes:
RTP F
xy 1 1.784, for Bu 1 8000 MHD/MTU 1 1.656, for Bu > 8000 MHD/MTU
- b. For the upper core region from greater than 50% to less than.or .
equal to 1001.:
- 1. For all planes containing bank "D" control tods: 1 F 1 1.952, for Bu 1 8000 MWD /MTU 1 1.95? ' r. c Bu > 8000 MHD/MTU
- 2. For all unrodded core planes:
~
RTP F
xy 1 1.732, for Bu 1 8000 MHD/MTU 1 1.778, for Bu > 8000 MHD/MTU These Fxy(z)-limits were used to' confirm that the heat flux hot channel factor FQ(z) will be limited to the Technical Specification values of:
F9 (z)1[2.Jol [K(z)] for P > 0.5 and, P
Fn(z)1[5.00] IK(z)] for P 1 0.5 assuming the most limiting axial power distributions expected to resuit ft om the insertion and removal of Control Banks C and D.during operation, including the accompanying variations in-the axial xenon and power distributions as~
described in the " Power Dit;tribution Control and Load Following Procedures",
WCAP-8403,. September, 1974. Therefore, these F x limits provide assurance-thatthe.initialconditionsassumedintheLOCAknalysisaremet,alongwith the ECCS acceptance criteria of 10 CFR 50.46.
See Figures'l and-2 for plots of [F .PRel).vs. Axial _ Core Height.
ZNLD/1764/6
- e e . _ .
' FIGURE 1 DYRON 2 CYCLE 4 Fxp LIMIT ANALYSIS - BU I 6000 = .
9.68 :
- ct . e. 2. so) :
2.50 -
_~% : ( 12. e, z. 31)
- ~
2 4g.
- Pk " ' '
2 30~ , - :
4 4" -
1- -
2.28- - :
I m 2.102- .
tu
a : - -
to 1.98 -
U 1. 88 : .
cc .
-i iI$1.78-m x1.68:- --
@ 1.58 ," - ,
a . '
1
"-1.43" ;
+- Top Surveillance Limi t .
, . ^
1'38- - -- --
+ Bottom Surveillance Limit :
}
1.20
[ CAOC Analysis Points :
1.10- .- - - i
- 1. g o . : _
- .- LOCA Limi t ing Enve Iope .
e N w v Y 6 8 9 10 11 12 <
0 1 2 3 4 5 7 i TOP BOTTOM CORE HEIGHT (FT) c 1
v
~
FIGURE 2 DYRON 2 CYCLE 4 Fxy LIMIT ANALYEIS - BU > 6000 =
2.68 :
2.56- 12.0* 2.31)
=
[ N . (
x g' 4 g . _ ._
- " . NA
- 2. 38' .
2.20 : -
w "
8 2.00; i -
c' : -
w 1.98~ :
m s 1.88; --
a .
Gi1.78- : .
m .
x 1. bii f -
6 1.50 l a .
"- 1 4 8 - : e- Top Surveillance Limi t .
1.38-
-+ Bot tom Surveillance Limit :
1.28 :
CAOC Analysis Points 1.13 ! -
-*-- LOCA Limi t ing Enve l ope :
1.00- : -
NNY MN4* ' q
f v v I 8 9 10 11 12 1 2 3 4 5 6 7
.'O EP 00HOM CORE ilEIGHT (FI)
l- .
I ATTACHBEH1,3 Refetencel I. Westinghouse HCAP-9272-P-A, " Westinghouse Reload Safety Evaluation Methodology," dated October 1985.
- 2. CECO /NFS 'opical report NFSR-0081, " Benchmark of PHR Nuclear Design Methods using the PHOENIX-P and ANC Codes," (dated July 1990) submitted for NRC review by letter from J. S11ady to T. E. Murley ,
dated July 13, 1990.
- 3. NRC SER on CECO's PHOENIX /ANC Topical 'Ref. 2) dated March il, 1991.
- 4. Westinghouse topical report HCAP-11596-P-A, " Qualification of the PH0ENIX/ANC Nuclear Design System for Pressurized Hater Reactor Cores," dated September 1936.
- 5. Westinghouse topical report HCAP-10965-P-A, "ANC: Westinghouse Advanced Nodal Computer C7de," dated September 1986.
e
- 6. CECO submittal, R.A. Chrzanwski to T.E. Murley, " Byron Station Units 1 and 2 Application to Facility Operating License NPF-37 and NPF-66,"
dated July 31, 1989.
- 7. NRC letter from L.N. 01shan to T.E. Kovach, Amendment No. 36 "Use of VANTAGE 5 Fuel," dated January 31, 1990.
t-ZNLD/1764/7
- - - - _ _ _ _ _
