ML20116F280
| ML20116F280 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/05/1992 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20116F277 | List: |
| References | |
| NUDOCS 9211100255 | |
| Download: ML20116F280 (5) | |
Text
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ATTACHMEN1 B Bw1C4 Core Operating Limits Report (COLR) 9211100255 921105 PDR P
ADOCK~05000456 PDR
.ZNLD/2278/7-
Braidwood Unit 1 Cycle 4
+-
-Operating Limit Report - fxy- Portion This_ Radial Peaking-Factor Limit Report-is provided in accordance with Paragraph 6.9;1.9 of the Braldwood Unit l' Nuclear Plant Technical Specifications.
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 tt.an or equal to 50%:
- 1. For all core planes containing bank "D" control rods:
RTP f
xy 1 2.1384 for Bu 1 8000 MHD/MTU 1 2.1384 for Bu > 8000 MHD/MTU
- 2. For all unrodded core planes:
RTP f
xy 1 1.9114, for Bu 1 8000 MHD/MTU 1 1.6922, 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 rods:
F 1 2.1384, for BU 1 8000 MHD/MTU
< 1 2.1384, for Bu > 8000 MHD/MTU-l t
- 2. For all unrodded core planes:
- F xy 1 1.8310, for Bu 1 8000 MHD/MTU l 1 1.8544, ror Bu > 8000-MHD/MTU j
l
! 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 oft Fg(z)1(2JD] [K(z)] for P > 0.5 and, P
Fg(z)1[5.001 [K(z)] for P 1 0.5 assuming the most limiting axial power distributions expected to result from 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 Distribution Control and Load Following Procedures",
HCAP-8403, September, 1974. Therefore, these F limits provide assurance thattheinitialconditions-assumedintheLOCA$nalysis-aremet,alongwith
-the ECCS_ acceptance criteria of-10 CFR 50.46.
Se Figures 1 and 2 for plots of IF .Pp,j] vs. Axial Core Height.
l- DRL:me.
L ZMJC:66:5 l .
^
Figure 21 Braidwood Unit 1 Cycle 4 Fxy Limit ' Analysis - Burnup s 8000 mwd /MTU 2.60
- i (6.0 , 2.5C ). l 2.50 x x '
^
(? 2.0, .
2.31) i 2.40 , -
w 2.30 .
=,
-x , ,
g' .r N
. 5 4 2:20 ; l-
} - 2.10 l l l
- o. : . .
e 2.00: : .. ..
$ 1.90 : l l -
. o.-
11.80 !
E l
1'70 : :
X Ei .
m - 1.60 : .
s :. .
- 1.50 5 l l
,_ E. x .- j 1.40 : '-
l E l x CAOC Analysis Points .
^
.1.30 : -
LOCA UmlHng Envelope f x 1.20 { .
- j ,10 l -- Boffom Surveillance Limit l
~
1.00 ; .[ -- Top Surveillance Limit l 0.90''''l'''''''''''''''''''''''''''''''''''''''''
-0 1. 2: .3. 4 5 6 7 '8 -9 10. 11 12 BOTTOM TOP Core Height (ff) ,
- f. - ,
4, ;
9 s 3 m E ~N, . , -
, e - -
,__________._____.______._..__.___._m ._L. .m_ , _ _
Figure 2 Braidwood Unit 1 Cycle 4 Fxy Limit Analysis - Burnup > 8000 mwd /MTU 2'60 j .l- (6.0 , 2.50) l 2.50 ^
(' 2.0, 2.31) 2.40 g . -
,x x w 2.30 :
l x
x 7x E .
- x 2.20 ; - ;
b l ,
x x
$ 2.10 ! {
{
o_ : , fx -
o 2.00 ::
.$ 1.90 l l
$ '1.80 !
- l 1.70 ! l
.
- x l
- m. 1.60 i l s : .
1.50 5 l l 1 E .
1.40 : l l E . x CAOC Analysts Points -
1.30 : -
LOCA Limiting Envelope 1 20 g:
l 1.10 5: l
-- Bottom SurvelNnce Limit l 1.00 l* l -- Top Surveillance Limit l E '
'''''''''''''''''''''''''''''' E'
- 0. 9 0 ' ' ' ' '
O 1 .2 3 4 5 6 7 8 9 10 11 12
, BOTTOM TOP-
,f Core Height-(ff)
_ __- _ ~ _ . . . - ___ _ _. _._ _. ..
4 ATTACHMENT C References 1.) Westinghouse WCAP-9272 P-A, dated October 1985;" Westinghouse Reload Safety Evaluation Methodology", (originally issued March 1978).
2.) CE^, submittal, J.A. Sllady to T.E. Murley dated July 13,1990; entitled
' Commonwealth Edison Com 3any Topical re > ort on Benchmark of PWR Nuclear- >
Design Methods Using The P1oenix P and A9C Computer Codes, NRC Docket-Nos. 50-295/304,50-454/455, and 50-456/457". ;
3.) NRC SER on CECO's Neutronics Topical (Ref.2) dated March 11,'1991. .
4.) CECO submittal, F.G. Lentine to H.R. Denton dated July 27,1983; entitled " Zion -
Stations Units 1 and 2, Byron Station Units 1 and 2, Braldwood Station Units 1 and 2, Commonwealth Edison compar'y Topical, Report on Benchmark of PWR-Nuclear Design Methods," NRC Docket Nos. 50-295/304,50-454/455, and 50-45G/457".
S.) NRC SER on CECO's Neutronics Topical (Ref. 5) dated Deember 13,1983.
6.) NRC Letter from S.P. Sands to T.E. Kovach, " Amendment No. 23 - Use of VANTAGE 5 Fuel", dated April 19,1990.
7.) CECO submittal, S.C. Hunsader to T.E. Murley "Braldwood Stations Unit 1 and 2 Application to Facility Operating License NPF-72 and NPF-77 dated October 1_4, 1989.
~
8.) Letter from T. Simpkin (CECO) to Dr. T. Murley (NRC), " Boron Dilution Protection
- System License Amendment Request," dated July 28,1992. '
9.) Letter from J.B. Hickman (NRC) to T.J. Kovach (CECO), " Issuance of
- Amendments, Braidwood Technical Specification Amendment 40 and Byron Technical Specification Amendment 51, to reflect changes to the current Boron Dilution Analyses, dated October 5,1992.
o 4
I a
_ZNLD/2278/8
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