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 ADOCK~05000456 P
.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
1 2.1384 for Bu 1 8000 MHD/MTU xy 1 2.1384 for Bu > 8000 MHD/MTU 2.
For all unrodded core planes:
RTP f
1 1.9114, for Bu 1 8000 MHD/MTU xy 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 l
1 2.1384, for Bu > 8000 MHD/MTU-t 2.
For all unrodded core planes:
RTP l
F 1 1.8310, for Bu 1 8000 MHD/MTU xy j
1 1.8544, ror Bu > 8000-MHD/MTU 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 l
i (6.0, 2.5C ).
2.50 x
i
(? 2.0,. 2.31) x
^
2.40 w
g'.r
-x,,
N
=,
2.30 5
4 2:20 ;
l-
}
- 2.10 l l
l o.
2.00:
e 1.90 l
l 11.80 !
l
. o.-
E 1'70 :
X Ei
- 1.60 :
m s
1.50 5 l
l E.
j x
l 1.40 :
E l
CAOC Analysis Points x
.1.30 :
^
1.20 {
LOCA UmlHng Envelope f
x 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 x
w
,x g
7x 2.30 :
l x
x E
x b
2.20 ;
l x x 2.10 !
{
{
fx o_
2.00 :
o 1.90 l l
'1.80 !
1.70 !
l l
x 1.60 i l
l m.s l
1.50 5 l
- 1 E
1.40 :
l l
CAOC Analysts Points E
x 1.30 :
1 20 g LOCA Limiting Envelope 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-Core Height-(ff)
,f
__- _ ~ _..
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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