ML20056D992
| ML20056D992 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/29/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056D990 | List: |
| References | |
| NUDOCS 9308190151 | |
| Download: ML20056D992 (2) | |
Text
5 UNITED STATES I
NUCLEAR REGULATORY COMMISSION En
- Uf WASHINGTON, D.C. 20566-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO OPPD-NA-8301-REV. 05 RELOAD CORE ANALYSIS METHODOLOGY OVERVIEW OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT 1 DOCKET NO. 50-285
1.0 INTRODUCTION
By letter dated February 5,1993, Omaha Public Power District (OPPD) submitted changes to Topical Report OPPD-NA-8301, " Reload Core Analysis Methodology.
Overview." This report provides an overview of OPPD's reload core methodology and describes the analyses performed by OPPD and its contractors. The proposed changes have been incorporated into Revision 5 of the report. These revisions reflect corporate name changes from Advanced Nuclear fuels-Corporation (ANF) to Siemens Power Corporation (SPC) and from Combustion-Engineering to ABB Combustion Engineering (ABB-CE).
In addition, a new section is added to indicate the use of a Core Operating Limits Report (COLR).
The Fort Calhoun Station, Unit 1 (FCS), is currently operating with.a core j
consisting' of ABB-CE and Westinghouse (W) 14x14 fuel assemblies.
2.0 EVALUATION
!'l The setpoint generation methodology has been updated. to reflect the replacement of-the QUIX code by'the HERMITE code for axial shape analysis.
This use of the NRC-approved HERMITE code is consistent with' applications of.
l this code by ABB-CE for analog protection system. plants and is, therefore, acceptable.
k The COLR section has been updated to reflect the approval of a COLR for FCS as j
part of the Cycle 14 reload license application.
In addition, the following' l
NRC-approved COLR parameters are listed:
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Thermal Margin / Low Pressure (TM/LP) Trip Setpoint Refueling Boron Concentration l
Limiting Condition'for Operation (LCO) for Excore Monitoring of Linear.
Heat' Rate (LHR) j i
LC0 for Deparature from Nucleate Boiling (DNB) Monitoring Core Inlet Temperature Power Dependent Insertion Limits Unrodded Integrated Radial Peaking Factor 9308190151 930729 DR ADOCK 0500 5
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Unrodded Planar Radial Peaking Factor Allowable Peak Linear Heat Rate vs. Burnup Core Power Limitations.(as a function of radial' peaking factors)'
i In accordance with the guidance in NRC Generic Letter'88-16, references to the-l approved topical. reports for the analytical methods used to determine these core operating limits have been updated to incorporateLthe latest approved'
'1 versions.
l References 2-4 and 2-5 to the ABB-CE fuel rod high burnup topical report were added to allow fuel rod average burnups of up to 60 MWD /kg for ABB-CE 14x14 t
fuel.
Recently, in a letter from A. C. Thadani (NRC) to S. A. Toelle (ABB-l CE), dated June 11, 1993, the NRC provided generic approval of the acceptability of a 1-pin burnup: limit of 60 MWD /kg for ABB-CE 14x14 pressurized water reactor fuel.
Future revisions to OPPD-NA-8301 should replace References 2-4 and 2-5 with the NRC generic safety evaluation for ABB-l CE 14x14 fuel.
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3.0 CONCLUSION
The staff has reviewed the proposed changes in Revision 5 to OPPD-NA-8301 and' finds them acceptable.
Principal Contributor:
L. Kopp Date: July 29, 1993
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