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Category:FUEL CYCLE RELOAD REPORTS
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[Table view]
Category:TEXT-SAFETY REPORT
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Rv Weld Chemistry & Initial Rt Ndt
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Monthly Operating Repts for Sept 1998 for Byron Nuclear Power Station,Units 1 & 2.With
ML20197C9051998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Byron Nuclear Power Station,Units 1 & 2.With
ML20151Z9651998-08-31031 August 1998
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ML20238F6551998-08-28028 August 1998
SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams
ML20237E2331998-08-21021 August 1998
Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept
ML20237B3361998-08-14014 August 1998
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ML20237B4841998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Byron Nuclear Power Station Units 1 & 2
1999-09-30
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Byron Unit 1 Cycle 7 Operatino Limits Reoort - Fxv Portion - Revision 1 !
l This Radial Peaking Factor Limits Report is provided in accordance with Paragraph 6.9.1.9 of 1 the Byron Unit 1 Nuclear Plant Technical Specifications.
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 bank "D" control rods:
F,,RTP s 1.950 Cycle Burnup - 0 MWD /MTU
- 2. For all unrodded core planes: 1 F,,""s 1.732 0$ Cycle Burnup s 10,000 MWD /MTU s 1.746 10,000 < Cycle Burnup < 16,000 MWD /MTU q ((((
$ 1.716 Cycle Burnup z 16,000 MWD /MTU i J
b: For the upper core region from greater than 50% to less than or equal to 100%:
- 1. For all core planes containing bank "D" control rods:
F,,"" 5 1.890 Cycle Burnup z 0 MWD /MTU
- 2. For all unrodded core planes:
f F,,""s 1.784 0 $ Cycle Burnup s 10,000 MWD /MTU s 1.807 10,000 < Cycle Burnup < 16,000 MWD /MTU s 1.769 Cycle Burnup > 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:
Fo(z) s [210] [K(z)] for P > 0.5 and P
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 variations in !
the axial xenon and power distributions as described in the " Power Distribution Control and Load 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.
l See the Attached Figure for the plot of [ F 70 *P%) vs. Axial Core Height.
9501040205 941228 k'nla wn:3$3 wpf;3 PDR ADOCK 05000454 P PDR
Rev.1 Byron Unit 1 Cycle 7 Fxy Limit Analysis 2.6 .
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(12A 331)
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2.3 B *
- m u l a 2.2 , , . '.
E a l u
u 2.1 ,
e :
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i "
o 2.0 . .
- o. . .
s Fxy Analysis Points "
g I ,
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a a 1.8 ,
- - - Top Surveillance Umit e4 .
o : - - Bottom Surveillance Umit .
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- .... ...I. .... . .. . .... . .. .. .. .... .... ....
0 1 2 3 4 5 6 7 8 9 10 11 12 P
- - Core Height (Feet)
_ _ _ _ _ _ _
