ML20059H848

SER Accepting Proposed Changes in Rev 3 to OPPD-NA-8302-P, OPPD Nuclear Analysis,Reload Core Analysis Methodology, Neutronics Design Methods & Verification

ML20059H848
Person / Time
Site:	Fort Calhoun
Issue date:	11/02/1993
From:	Office of Nuclear Reactor Regulation
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ML20059H847	List: ML20059H843 ML20059H848
References
NUDOCS 9311100244
Download: ML20059H848 (2)

Text

• 90 REC (g fl _ [\ UNITED STATES i I dJlf 'i E NUCLEAR REGULATORY COMMISSION i '.N 4 '/ I WASHINGTON. D.C. 20566-0001 ENCLOSURE

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO OPPD-NA-8302-P. REVISION 03 NEUTRONICS DESIGN METHODS AND VERIFICATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT 1 DOCKET NO. 50-285

1.0 INTRODUCTION

In a letter of February 5,1993 (Ref.1), Omaha Public Power District. (OPPD) submitted proposed changes to Topical Report OPPD-NA-8302-P, "0 PPD Nuclear Analysis, Reload Core Analysis Methodology, Neutronics Design Methods and Verification," (Ref. 2). Revised pages, including minor editorial corrections and inclusion of non-proprietary versions, were transmitted in a letter of June 25, 1993 (Ref. 3). The report describes the OPPD reload core neutronics design methodology for application to the calculation of specific physics parameters for reload cores for the Fort Calhoun Station, Unit No.1.

Comparisons of results obtained using these methods with results of experimental measurements and with independent calculations are presented.

The proposed changes would be incorporated as Revision 03.

Fort Calhoun is currently operating with a core consisting of ABB Combustion Engineering (ABB-CE) and Westinghouse Electric Corporation (W) 14x14 fuel assemblies.

2.0 EVALUATION The CE setpoint generation methodology (Ref. 4) has been updated to reflect the replacement of the QUIX code by the HERMITE code (Ref. 5) for axial shape analysis. This use of the NRC-approved HERMITE code is consistent with the applications of this code by ABB-CE for other analog protection plants and is, therefore, acceptable. The neutronics design methodology reference for the ROCS /DIT/HC codes has also been changed to the most recent approved CE topical report (Ref. 6).

Various other minor revisions have been made to reflect current approved methodology, to make editorial corrections, and to update references to the most recent revisions. These various changes have been found to be acceptable.

9311100244 931102 PDR ADOCK 05000285 P PDR

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3.0 CONCLUSION

The staff has reviewed the proposed changes in Revision 03 to OPPD-NA-8302-P  !

and finds them acceptable, as stated in the above evaluation.

4.0 REFERENCES

1. Letter from W. G. Gates (OPPD) to Document Control Desk (NRC), "0 PPD Revised Core Reload Analysis Methodology Topical Reports for Cycle 15,"

LIC-93-0015, February 5, 1993.

2. OPPD-NA-8302-P, Revision 3, "0 PPD Nuclear Analysis, Reload Core Analysis Methodology, Neutronics Design Methods and Verification," January 1993.

3. Letter from W. G. Gates (0 PPD) to Document Control Desk (NRC), " Revised Pages for Fort Calhoun Station Cycle 15 Core Reload Analysis Methodology ,

Topical Reports," LIC-93-0165, June 25, 1993. 3

4. CENPD-199-P, Revision 1-P-A, "CE Setpoint Methodology," January 1986.  ;

5. CENPD-188-A, "HERMITE, A Multi-Dimensional Space-Time Kinetics Code for )

PWR Transients," March 1976. ,

6. CENPD-266-P-A, "The ROCS and DIT Computer Codes for Nuclear Design," -

April 1983.

Principal Contributor: E. Kenrick l

Date: November 2, 1993  ;

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