ML20153E164: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 4
| page count = 4
| project =
| stage = Request
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Latest revision as of 17:16, 10 December 2021

Forwards Nonproprietary & Proprietary OPPD-NA-8301-NP & OPPD-NA-8302-P,respectively.Util Will Now Utilize Mc Code Consistent W/Methods Currently Being Used by C-E.Application for Withholding Info from Public Disclosure Encl
ML20153E164
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 08/30/1988
From: Morris K
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20153E168 List:
References
LIC-88-706, NUDOCS 8809060228
Download: ML20153E164 (4)


Text

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1 l

- o Omaha Public Power District l

1623 Harney Omaha, Nebraska 68102 2247 I 402/536 4000 August 30, 1988 LIC-88-706 1

l U. S. Nuclear Regulatory Comission 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 Relead Core Analysis Methodology, Neutronics Design Methods anJ Verification," OPPD-NA 8302-P, November, 1986.
4. "0 PPD Nuclear Analysis Reload Core Analysis Methodology, Transient and Accident Analysis Methods and Verification,"

OPPD-NA-8303-P, November 1986.

5. Letter from OPPD (K. J. Morris) to NRC (Document Control Desk) dated July 8, 1988 (LIC 88-442).
6. t.etter from NRC (P. D. Milano) to OPPD (K. J. Morris) dated August 3, 1588 Gentlemen:

SUBJECT:

Core Reload Methodology Changes for Cycle 12 The Omaha Public Power District (0 PPD) is currently oorforming the Cycle 12 core reload safety analysis for the Fort Calhoun Station. Changes to the reload methodology topical report (References ? through 4) are required to reflect the use of a more efficient computer code utilized for core analysis.

To facilitate the review of changes, OPPD previously transmitted, in Reference 5, a hand marked version of the proposed changes. In addition, the NRC technical staff has requested, in Reference 6, additional information on the proposed Steam Generator Tube Rupture Event methodology and determined that its inclusion into the Cycle 12 reload analysis submittal was not necessary.

Accordingly, that section has been omitted from this submittal, and the requested information will be transmitted separately.  ;

OPPD previously 'ilized 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 c Acol

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, LIC-88-706 Page 2 1

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 diffusion 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 editor-  ;

~

tal in nature. Revisions are denoted by a vertical line in the right hand margin with a summary of proposed changes contained in Tables 1 through 3.

Please note that pursuant to 10 CFR 2.790(b)(1), portions of the attached i information included in Topical Report OPPD NA 8301-P through 8303 P have been j deemed trade secrets and/or privileged commercial information by Combustion '

Engineering, Inc. (CE) and Advanced Nuclear Fuels Corp. (ANFC). Proprietcry l portions are denoted by their inclusion within brackets ([ ]).  ;

Accordingly, please find attached OPPD's application for withholding this i information from public disclosure. A nonproprietary version of the Topical Reports, OPPD NA 8301-NP through 8303 NP is also included, with the proprietary l information being replaced by a summary of its contents. If you have any i questions concerning this matter, do not hesitate to contact us. l i

Sincerely, j f/I Y .

K. J. Morris  :

Division Manager e Nuclear Operations ,

l KJM/me l i

Attachments  !

c: P. D. Milano, NRC Project Manager c w/o attachments LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector l

l l

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l

. 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 WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE Pursuant to Section 2.790(b)(1) of the regulations of the Nuclear Regulatory Commission ("the Commission"), Omaha Public Power District ("the District") ,

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 t h t 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 l following documents:

OPPD Nuclear Analysis, Reload Core Analysis Methodology Overview -

OPPD-NA 8301-P, Revision 3, dated April 1988.

OPPD Nuclear Analysis, Reload (ore Analysis Methodology, Neutronics Design Methods and Verification, OPPD-NA 8302-P, Revision 3, dated April 1988.

OPPD Nuclear Analysis, Reload Core Analysis Methodology, Transient and Accident Methods and Verification, OPPD NA-8303 P, Revision 2, dated April 1988.

These documents have been appropriately designated as proprietary. j l

2-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.

OHAHA PUS IC POWER D,ISTRICT By/ M/#>

K .' { MofrTs Div)isionManager Nuclear Operations Sworn to before me on this 2n day of August 1988

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