ML20097D772
| ML20097D772 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/19/1995 |
| From: | Thomasen J COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20097D760 | List: |
| References | |
| NUDOCS 9602130172 | |
| Download: ML20097D772 (5) | |
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216636 NUCIIAR FUEL SERVICES DEPARTMENT NUCLEAR DESIGN INFORMATION TRANSMITTAL E SAFETY RELATED Originatmg Orannmtion NDIT No.95-074 O NON-SAFETY RELATED E NuclearFuelServices Rev. No.
O O REGULATORY RELATED O Other(specify)
Page1of5 Station Byron Unit 1
Cycle 7 Generic To: O. W. Stauffer Subject Byron Unit 1 Cycle 7 Operatina linits Report Revision 3 John P. '!homanen 12/19/95 Preparer
's Signature Date S. Yang 4W 12/19/95 n -.
Reviewer Reywwer's Signature [
y Date
\\
D. R Redden 12/19/95 NFS Supervisor NFS Supervisor's Signature Date Status ofInformation:
E Verified O Unvenfied O EngswarmgJudgement Method and Schedule of Verification for Unverified NDITs:
Description ofinformation: Revision 3 of the Byron Unit I Cycle 7 Operstmg Limits Report. The maximum Fainformaten contamed in Table 1 and Figure 1 remams the same as that in Revision 2 of the BYlC7 OLR. "Ihsrefore, Revision I of Fiya 4.1 and Revision 1 of Table B.1 of the Nuclear Design Report, NFSR-0106, remain valid and do not need to be changed. Byron Station is requested to perform an On-Site Review of this document. Upon completion of the OSR, Byron Station is to notify the NLA who will then transmit the OLR to the NRC pursuant to Technical Specifwation 6.9.1.9.
Purpose ofInformation: Provides the revised Operating Umits for Cycle 7 for burnup >= 13,200 MWDMTU. New values reflect the 2 degree Tave increase following B1P02.
Source ofInformation: PWR Nuclear Design Calc. Note. Project: BYlC7B NDR, Calculation Number: NR-4S, File: BYlC7NDN 10.6 l
Supplemental Distribution: M.I h air S. Yang @. L Manges K. N. Kovar/S. Ahmed NDIT File PSS{F NFS-CF(w/o Att)
Byron Central File CliRON No:
l 9602130172 960209 DR ADOCK 05000454 PDR
~
l
NUCLEAR NEL SERVICES DEPARTMENT NDir No.
95470 NUCLEAR DESIGN INFORMATION TRANSMrTTAL Rev. No.
O Page 2 of 5 Byron Unit 1 Cycle 7 Operatine Limits Report - Fry Portion This Radial Peaking Factor Limits Report is provided in accordance with Paragraph 6.9.1.9 of the Byron Unit 1 Nuclear Plant Technical Specifications.
1 The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 7 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 bar& "D" control rods:
F "" s1.950 CycleBurnup 2 0 MWD /MTU y
- 2) For all unrodded core planes:
l F ""s1.736 13,200 s CycleBurnup <
16,000 MWD /MTU y
s 1.712 CycleBurnup 2 16,000 MWD /MTU l
b: For the upper core region from greater than 50% to less than or equal to 100%:
j
- 1) For all core planes containing bank "D" control rods:
F "" s1.890 CycleBurnup 2 0 MWD /MTD y
- 2) For all unrodded core planes:
Fy""s 1.804 13,200 s Cycle Burnup <
16,000 MWD /MTU s 1.769 Cycle Burnup 2 16,000 MWD /MTU These Fxy(z) limits were used to confirm that the heat flux hot channel factor Fo(z) will be limited to the Technical Specification values of:
Fn(z) s [210] [K(z)]
for P > 0.5 and, Fo(z) s [5.00] [K(z)]
for P s 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 vanations in the axial xenon and power distributions as described in the " Power Distribution Control and 1. cad Following Procedures".
WCAP-8403, September,1974. Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10 CFR 50.46.
See the Attached Figure 1 for the plot of[ Fo(z) x P] versus Core Height.
l
NUCLEAR IML SERVICES DEPARTMENT NDIT No.95-074 NUCLEAR DEsION INFORMATION TRANSMTITAL Rev. No.
O Pase 3 of 5 Revision 3 Byron Unit 1 Cycle 7 Ooerstian Limits Report - MTC Portion a)
The Moderator Temperature Coefficient (MTC) limits are:
- 1) The BOUARO/HZP-MTC shall be less positive than 0 Ak/k/'F.
- 2) The EOUARO/RTP-MTC shall be less negative than -4.1 x 10" Ak/k/'F.
i b)
The MTC surveillancelimit is:
The 300 ppm /ARO/RTP-MTC should be less negative than or equal to d
-3.2 x 10 Ak/k/'F.
where:
BOL stands for Beginning of Cycle Life ARO suinds for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 4
NUCIIAR FUEL SERVICES DEPARTMENT hTIT No.95-074
- a NUCLEAR DESION INFORMATION TRANSMTITAL Rev. No.
O i
Pete 4 of 5 l
l Revision 3 Byron Unit 1 Cycle 7 Operating Limitt Report Table 1 - Maximum Fn
Fo
- P BOTTOM i
0.1252 0.41 2
0.3756 0.77 3
0.6259 1.83 4
0.8763 2.13 5
1.1267 237 i
6 13771 2.47 7
1.6274 2.50 8
1.8778 2.47 9
2.1281 2.27 10 2.3786 2.40 11 2.6289 2.44 i
12 2.8793 2.47 l
13 3.1297 2.48 14 33801 2.49 15 3.6305 2.50 16 3.8808 230 17 4.1312 2.49 18 43816 2.49 19 4.6320 2.48 20 4.8823 2.46 t
21 5.1327' 2.44 22 53831 2.40 23 5.6335 2.18 24 5.8838 2.35 25 6.1342 2.44 26 63846 2.45 27 6.6350 2.46 28 6.8853 2.46 29 7.1357 2.44 30 73861 2.28 31 7.6365 2.42 32 7.8868 239 33 8.1372 235 34 83876 2.32 35 8.6380 2.32 36 8.8883 2.27 37 9.1387 2.19 38 93891 231 39 9.6395 2.31 40 9.8898 2.34 41 10.1402 236 42 103906 236 43 10.6410 2.23 44 10.8914 2.13 45 11.1417 1.94 46 11.3921 1.66 47 11.6425 0.71
'IDP 48 11.8929 0.41 j
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