ML20214H464

Forwards Proprietary Rev 2 to OPPD-NA-8301-P, Omaha Public Power District Nuclear Analysis Reload Core Analysis Methodology Overview, Incorporating Methodology Changes for Cycle 11.Rept Withheld (Ref 10CFR2.790(b)(1)).Fee Paid

ML20214H464
Person / Time
Site:	Fort Calhoun
Issue date:	11/17/1986
From:	Andrews R OMAHA PUBLIC POWER DISTRICT
To:	Thadani A Office of Nuclear Reactor Regulation
Shared Package
ML19292G298	List: ML20214H464
References
LIC-86-537, TAC-63937, TAC-63967, NUDOCS 8611260413
Download: ML20214H464 (8)

Text

Omaha Public Power District 1623 Harney Omaha. Nebrasha 68102 2247 402/536 4030 November 17, 1986 LIC-86-537 Mr. Ashok C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing - B Office of Nuclear Reactor Regulation V. S. Nuclear Regulatory Commission Washington, DC 20555

References:

1. Docket No. 50-285

2. "0 PPD Nuclear Analysis Reload Core Analysis Methodology Overview", OPPD-NA-8301-P, June 1985.

3. "0 PPD Nuclear Analysis Reload Core Analysis Methodology, Neutronics Design Methods and Verification," OPPD-NA-8302-P, September 1983.

4. "0 PPD Nuclear Analysis Reload Core Analysis Methodology, Transient and Accident Analysis Methods and Verification,"

0 PPD-NA-8303-P, September 1983.

Subject:

Core Reload Methodology Changes for Cycle 11

Dear Mr. Thadani:

The Omaha Public Power District is currently performing the Cycle 11 core reload safety analysis for the Fort Calhoun Station. The Cycle 11 core desiga utilizes a symmetric low radial leakage loading similar to that of Cycle 9.

This design minimizes the flux to the reactor vessel beltline welds, thus mini-mizing the RTNDT shift. Beginning with Cycle 11, Combustion Engineering (CE) will again be providing Fort Calhoun Station with reload fuel (Batch M). CE last provided new fuel for Cycle 5 (Batch G). The only design difference between the Batch G and M fuel relates to the design of the lower end fitting.

The Batch M end fitting has been tested and found to be " hydraulically" '

identical to the Batch G end fitting. Exxon Nuclear Co. (ENC) provided Fort Calhoun Station with new fuel for Cycles 6 through 10. Because the ENC fuel was compatible with the CE Batch G fuel and the CE Batch M fuel is essentially the same as Batch G, the CE Batch M fuel is considered to be compatible with the remaining ENC fuel which will be reloaded in the Cycle 11 core.

As a consequence of the measurement of high CEA strains during the 1985 refuel-ing outage, all CEA's not replaced in 1985 will be replaced at the end of Cycle

10. The four part-length CEA's will be replaced by full-length CEA's whose physical dimensions are identical. Technical Specifications prohibit the use

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Ashok C. Thadani LIC-86-537 Page 2 of the part length CEA's (Group P) during operations. Use of full-length CEA's in place of the part length CEA's will have no impact on operation, i.e., Tech-nical Specifications will still require that Group P be withdrawn above 114 inches. Credit for additional shutdown margin may be taken for these rods when they are driven in by the operators following a reactor shutdown.

For Cycle 11, CE is reanalyzing three events for OPPD. These events, which are ones that OPPD does not currently analyze in house, include the large Break Loss of Coolant Accident (LOCA), the Small Break LOCA, and the CEA Ejection.

The Large Break LOCA is being analyzed using CE's revised evaluation model, which has been approved by the NRC. The Small Break LOCA methodology is the sama as for the current analysis; and the CEA Ejection analysis methodology is the same as was used for Cycle 5. These analyses are being performed to allow up to 6% tube plugging per steam generator in order to bound future steam generator work. Currently,1% of the tubes are plugged.

In order to assess the effects up to 6% of steam generator tube plugging, two additional events will be examined to ensure the design basis remains valid.

These events are the loss of Load and Loss of Main Feedwater Events.

Because of the Cycle 11 changes described above, Omaha Public Power District reload methodology topical report (References 2-4) changes are also required.

Copies hand marked in the format requested by Mr. D. E. Sells of your staff are included in Attachments 1, 2, and 3 for existing pages. New pages contain a border around the added material and have page numbers consisting of alphanu-meric characters, e.g., 63A. Tables 1, 2, and 3 summarize the pages changed and the. reasons. Revised and retyped reports will be transmitted upon your approval of this submittal.

Please note that pursuant to 10 CFR 2.79-0(b)(1), certain portions of the at-tached information has been deemed trade secrets and/or privileged commercial information by Combustion Engineering, Inc. (CE) and Exxon Nuclear Company, Inc. (ENC). Accordingly, please find attached the District'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.

Sincerely, Aka R. L. Andrews Division Manager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.

Washington, DC 20036 A. C. Thadani, NRC Project Director D. E. Sells, NRC Project Manager 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 WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE Pursuant to Section 2.790 (b)(1) of the regulations of the U. S.

Nuclear Regulatory Commission ("the Consission"), Omaha Public Power District, ("the District") holder of Facility Operating License No.

DPR-40, submits this application to withhold certain information from public disclosure. Applicant has obtained this information from documents which identify this information as being owned by Combustion Engineering, Inc. (CE) or by Exxon Nuclear Company, Inc. (ENC). It is the opinion of CE and ENC that the information in question contains trade secrets and/or j privileged or confidential commercial or financial information. The CE and ENC 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-NA-8301-P, Rev. 01, Reload Core Analysis Methodology Overview, June, l 1985.

i OPPD-NA-8302-P, Rev. 00, Reload Core Analysis Methodology, Neutronics Design Methods and Verification, September 1983.

OPPD-NA-8303-P, Rev. 00, Reload Core Analysis Methodology, Tra :sient and Accident Analysis Methods and Verification, September 1983.

The documents have been appropriately designated as proprietary.

This information was obtained by the District from documents for which CE and ENC 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 R. L. Andrews Division Manager Nuclear Production Subscribed and sworn to before me this \' lib day of Lboembr , 1986.

I satausmer-m nd m Il us.vA L EVANS "15%

• C'" '"M'E Notary Public l

TABLE 1 OPPD-NA-8301-P EXPLANATION OF REVISIONS Pace No. Reason for Chanae All Update the new revision number.

1 The current nuclear fuel vendor, the fuel mechanical design and design methods are from current nuclear fuel vendor.

Change verb referring to Cycle 10 to past-tense.

9 Typographical error correction of the units for Avg. Mass velocity.

10 Delete a redundant sentence.

15 New reference No. la. and relabel old reference No. I to Ib.

16 Revised reference No.16.

Figure 1 Additional information added to title.

Figure 2 Additional information added to title.

3 JABLE 2 OPPD-NA-8302-P EXPLANATION OF REVISIONS Paae No. Reason for Chance

v. Add revision sheet.

5 Typographical error correction.

6. Add CE shimmed fuel assemblies cross-sections.

7 Use chemical expression of 8 4C.

11 ROCS computer code' replaces BETAF computer code.

3 i

e I

i j

v i

I.

TABLE 3 _

OPPD-NA-8303-P EXPLANATION OF REVISIONS Paae No. Reason for Chanae iii Revise topic heading of part-length CEA's due to their replacement with full-length CEA's, iv Add sections 5.12 and 5.13.

v Add revision sheet.

2. Typographical error correction.

3. Revise part-length CEA section.

4-5 Typographical error correction.

4a Add paragraph to loss of load to both steam generator event to evaluate steam generator tube plugging effects.

Sa Add paragraph to loss of feedwater flow event to evaluate f steam generator tube plugging effects.

6. Loss of coolant accident analyses performed by CE.

16, 22, 26, 35, 40 Peak Linear Heat Generation Rate revised to be consistent with CE fuel mechanical design report.

61 - 62 Revise methodology used by current fuel vendor (CE).

63 Analyses performed by CE.

63a - 63e Add secticn 5.12 for analyzing loss of load to both steam generators event to accommodate expected steam generator tube plugging beyond current limit of 1%.

63e - 63j Add section 5.13 for analyzing loss of feedwater flow event to accommodate expected steam generator tube plugging beyond current limit of 1%.

117 Typographical error correction and topical update "Rev.

01".

118 Change CEA ejection methodology topical report to that used by CE.

Update reference OPPD-NA-8302.

Add reference CEN-347(0)-P.

Add reference letter on CE large break LOCA analysis.

T ATTACHMENT I I

l

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