ML20150C042

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Forwards Changes to Reload Methodology Topical Rept to Reflect Use of More Efficient Computer Code Utilized for Core Analysis.Encl Documents Withheld (Ref 10CFR2.790)
ML20150C042
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 07/08/1988
From: Morris K
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML19292J022 List:
References
LIC-88-442, NUDOCS 8807120292
Download: ML20150C042 (4)


Text

Omaha Public Power Ulstrict 1623 Harney Omaha. Nebraska 68102 2247 402/536 4000 July 8, 1988 LIC-88-442 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555

References:

1.

Docket No. 50-285 2.

"0 PPD Nuclear Analysis Reload Core Analysis Methodology Overview", OPPD-NA-8301-P, November 1986.

3.

"0 PPD Nuclear Analysis Reload Core Analysis Method 31ogy, Neutronics Design Methods and Verification," 0 PPD 4A-8302-P, November, 1985.

4.

"0 PPD Nuclear Analysis Reload Core Analysis Methodology, Transient and Accident Analysis Methods and Verification,"

0 PPD-NA-8303-P, November 1986.

SUBJECT:

Core Reload Methodology Changes for Cycle 12 Gentlemen:

The Omaha Public Power District (OPPD) is currently performing the Cycle 12 core reload safety analysis for the Fort Calhoun Station.

Changes to the reload methodology topical report (References 2 through 4) are required to reflect the use of a more efficient computer code utilized for core analysis.

Previously, OPPD utilized the PDQ-X code to produce two-dimensional fine mesh core design information.

OPPD will now utilize the MC code which is consistent with the methods currently being used by Combustion Engineering.

The MC code is covered by the ROCS DIT Topical Report, and OPPD is an authorized utility to use these codes under the topical report.

The capabilities of MC offer a more computationally efficient alternative to conventional fine mesh dif fusion theory computer codes, such as PDQ-X, which in practice are limited to two-dimensional core analyses.

MC also eliminates the practice of representing large gradients in the vicinity of CEA guide tubes and burnable absorber pins, resulting in the use of less computer time per calculation.

Reference 3 has been revised to reflect the use of the MC code.

Remaining changes are editorial in nature.

Hand marked copies of References 2, 3, and 4 are included I

in the attachments.

This will facilitate the review of the submittal by boldly l

denoting where revisions have been made by OPPD to the reports.

Tables 1, 2, and 3 summarize the pages changed and the reasons.

1 Please note that pursuant to 10 CFR 2.790(b)(1), the attached information in its entirety has been deemed trade secrets and/or privileged commercial information by Combustion Engineering, Inc. (CE) and Advanced Nuclear Fuels fiOl Corp. (ANFC),

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U. S. Nuclear Regulatory Commission LIC-88-442 Page 2 l

Revised and retyped reports (both proprietary and nonproprietary versions) will be submitted upon approval of this submittal.

To facilitate our preparation of these documents, and to support reload efforts, your review of these reports by July 30, 1988 would be greatly appreciated. Accordingly, please find attached OPPD's application for withholding this information from public disclosure.

Enclosed herewith also is a check in the amount of $150.00 per 10 CFR 170, for review of this document.

If you have any questions concerning this matter, do l

not hesitate to contact us.

Sincerely, M%

K(e J. Morris Division Manager Nuclear Operations KJM/me Attachments c:

P. D. Milano, HRC Project Manager c w/o attachments LeBeeuf, tamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the matter of

)

)

OMAHA PUBLIC POWER DISTRICT

)

Docket No. 50-285 (Fort Calhoun Station,

)

Unit No. 1)

)

APPLICATION FOR WITHH0LDING INFORMATION FROM PUBLIC DISCl0SVRE Pursuant to Section 2.790(b)(1) of the regulations of the Nuclear Regulatory Commission ("the Commission"), ')maha Public Power District ("the Nstrict")

submits this application to withhold certain information from public dis-closure.

Applicant has obtained this information from documents which identify this information as being owned by Combustion Engineering, Inc. (CE) or by Advanced Nuclear Fuels Corporation, (ANFC), formerly Exxon Fuel Company, Inc.

It is the opinion of CE and ANFC that the information in question contains trade secrets and/or privileged or confidential commercial or financial infor-mation. The CE and ANFC information was purchased by the District under a proprietary information agreement.

The information for which proprietary treatment is sought is contained in the following documents:

OPPD Nuclear Analysis, Reload Core Analysis Methodology Overview -

OPPD-NA-8301-P, Revision 2, dated November, 1986.

OPPD Nuclear Analysis, Reload Core Analysis Methodology, Neutronics Design Methods and Verification, OPPD-NA-8502-P, Revision 1, dated November, 1986.

OPPD Nuclear Analysis, Reload Core Analysis Methodology, Transient and Accident Methods and Verification, OPPD-NA-8303-P, Revision 1, dated November 1986.

These documents have been appropriately designated as proprietary.

--- This information was obtained by the District from documents for which CE and ANFC have executed affidavits which set forth the bases on which the information may be withheld from public disclosure by the Commission.

Respectfully Submitted, OMAHA PUBLIC POWER DISTRICT By /

/

K.'r,Atorris '

Di #sion Manager Nuclear Operations 4h Sworn to before me on this 9

day of July 1988 PbDtt f,,

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Notary j