ML19253C761
| ML19253C761 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/26/1979 |
| From: | Erickson P Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912120080 | |
| Download: ML19253C761 (4) | |
Text
MEETI!4G SUt'"ARY DISTRIEUTICN
~
CRBs4 f!r.
k'. C. Jones Division !'.anager, Production Operations Omaha Public Power District 1623 Harney St.
F Cmaha, t;ebraska 68102 j
"~ ba* File R. Reid FG V. tioonan L PDR P. Check DRE#4 Rc; G. Lainas i;RR Rdg G. Knighton H. Denton Project Manager E. G. Case OELD 01&E (3)
D. Eisenhut R.
Ingram R. Vollm r R. Fraley, ACRS (16)
W. Russell Program Support Branch B. Grimes TERA T. J. Carter J. R. Buchanan A. Schwencer Meeting Summary File D. Zie ann NRC Participants T. Ippolit R M el W. Gammill SWeiss L. Shao SSands Miller VWPanciera v.
1537 164
'0121:;0 0 80
UNITED STATES 3
^
tsUCLEAR REGULATORY COMMISSION j
.N ASHINGTON. D. C. 20 355 f
Noverber 26, 1979
- ocket :o.53-255 LICEllSEE: Omaha Public Power District (0 PPD)
FACILITY: Fort Calhoun
SUBJECT:
MItiUTES OF tiOVEMBER 16, 1979 MEETIrlG TO DISCUSS FORT CALH0Utl CYCLE 6 RELCAD AND PROPOSED POWER If: CREASE Subject reeting was held in Bethesda, Maryland. Those in attendance are listed in Enclosure 1.
OPPD discussed the EXX0tl analysis of the Cycle 6 reload and the proposed increase in power from 1420 Megawatts thermal (!bt) to 1500 Mwt.
The OPPD schedule for submittal of a small break analysis was of significant interest because the analysis, as proposed, would be based on EXX0!! methods which have not been presented to the NRC.
Various options for submittal of the small break analysis were considered including the use of approved Combustion Engineering (CE) analysis and the results of TMI-2 studies. lists the options for ? 311 break analysis.
In addition, OPPD was told that they must show that the small break analysis meets 10 CFR 50.46 and 10 CFR 50 Appendix K reouirements.
The staff discussed the planned NRC audit of setpoint calculations for Cycle 6 and NRC plans for a meeting with OPPD and EXXON to answer staff concerns about EXX0t! calculations of setpoints.
The proposed irradiation of one standard fuel assembly for a fourth cycle was also discussed.
P. B. Erickson, Project !!anager Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
List of Attendees 2.
O R 5-Ereak Octions 1537 165
=
m m res:
m LC-
'"~.'.*2 3
LIST OF ATTE!! DEES 11/16/79 OPPD EETI:;G 50-285 NRC OPPD Peter B. Erickson Josepa Gasper Richard Lobel Bruce J. Hickle Stephen Sands S. H. Weiss V. W. Panciera LeBOEUF. LAMB. LEISY & MACRAE Harry H. Voigt EXXOH NUCLEAR Margaret R. A. Paradis Gerald Owsley Jim Morgan Thomas L. Krysinski PRICKARD. LOWE & GARRICK (OPPD)
Finn B. Skogen The as Robbins 1537 166 (OVER)
OPPD SMALL BREAK OPTIONS (NRC VERSION)
N0 STRETCil POWER SIRETCil POWER I
I I
Worst Small Redo Calculation Worst Break is CE report applicable Break with According to Post with Drift to Cycle 6 with Exxon Dri f t flux thiel THI M> del at liigher flux thiel fuel ?
Post IMI Power Level Post IMI Deficiences included De f it. i enc i es Included U1 i
Reference CE CE Report report and ex-Not Applicable plain why it is to Exxon fuel, cd a ppl ic a bl e.
Redo Calculations N
with CE Hethods, Incorpurate Exxon fuel.
7:
<a D3
,