ML20204F393
| ML20204F393 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/18/1987 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19292G995 | List: |
| References | |
| LIC-87-166, TAC-63937, TAC-63967, NUDOCS 8703260187 | |
| Download: ML20204F393 (4) | |
Text
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102-2247 1
402;536 4000 March 18, 1987 LIC-87-166 Mr. Ashok C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing - B Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
References:
1.
Docket No. 50-285 2.
OPPD letter (R. L. Andrews) to NRC (A. C. Thadani) dated November 17, 1986 (LIC-86-537) 3.
OPPD letter (R. L. Andrews) to NRC (A. C. Thadani) dated December 15, 1986 (LIC-86-677) l
Dear Mr. Thadani:
1
SUBJECT:
Core Reload Methodology Changes for Cycle 11 In Reference (3) the Omaha Public Power District (0 PPD) provided the " Core Reload Methodology Changes for Cycle 11".
Subsequent reviews were made of that submittal and some typographical errors were found.
Attached you will find a summary and copies of the corrected pages for the three (3) sets of proprietary and the three (3) sets of non-proprietary material previously submitted.
These changes do not effect materials originally submitted, since they are only typographical corrections.
Sincerely, R. L. Andrews Division Manager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
Washington, DC 20036 f.
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the matter of
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OMAHA PUBLIC POWER DISTRICT
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Docket No. 50-285 (Fort Calhoun Station,
)
Unit No. I)
)
APPLICATION FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE Pursuant to Section 2.790(b)(I) 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 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 summarized in the attached document:
Omaha Public Power District Nuclear Analysis Reload Core Analysis Methodology Change Out Page Summary
t-This information was obtained by the District from documents for which CE and ANFC has executed affidavits which set forth the bases on which the information may be withheld from public disclosure by the Commission.
Respectfully Submitted, OMAHA PUBLI P ER DISTRICT By A 'S R. L. Andrews Division Manager Nuclear Production Sworn to before me on this ig4b day of March 1987
$1NERAl tetARf = State si ngheechs 9m,c..".. tie $.YsB V^ '
Notary
Omaha Public Power District Nuclear Analysis Reload Core Analysis Methodology Change Out Page Summary t
OPPD - NA - 8301 - P Rev. 02 page 9, table 2 propriatary brackets extended to include
" Detailed TORC - Location 5" Column l
OPPD - NA - 8302 - P Rev. 01 j
page 10, section 4.2
" correlation"--+ " correlations" 0 PPD - NA - 8303 - P Rev. 01 page 11, section 4.1
" saturated," --* " saturated;"
page 17, section 5.1.1
" attention"
" attenuation"
~
l page 42, table 5.5.4-1 "LL/ISG" "LL/1SG"
=
"LL/1SG"(lines 1and5) l page 43, section 5.5.6 "LL/ISG" page 45, section 5.6.1 "70'F" "17'F" l
page 47, section 5.6.4 delete "CENPD-199-P" (redundant to ref. 5-2) page 48, table 5.6.4-1 delete " values up to the" l
page 49, section 5.6.6 delete "CENPD-199-P" (redundant to ref. 5-2) page 50, section 5.6.7 delete "CENPD-199-P" (redundant to ref. 5-2) page 62, section 5.8.6
" lift"
=
" limit" page 68, section 5.10.2 "Entholphy" ~ "Enthalpy" and "Enthology" ---* "Enthalpy" page 70, section 5.11
" topic"
~ " topical" and i
" Appendix K" ---* "10CFR50.46" nage 72, section 5.12.2
" limit.A00" ~ " limiting A00" i
page 74, table 5.12.4-1 Core Average Hgap
" Minimum"
= " Maximum" (seenote) page 76, section 5.13
" Loss of Feedwater Flow" --o " Loss of Feed-water Event" and " Definition of Test" %
l
" Definition of Event" f
page 77, section 5.13
" Loss of Feedwater Flow" --* " Loss of Feed-i j
water Event" and " Definition of Test".--*
" Definition of Event" i
page 78, section 5.13
" Loss of Feedwater Flow"-+" Loss of Feedwater Flow Event" page 79, section 5.13
" Loss of Feedwater Flow"-9" Loss of Feedwater Flow Event" page 80, section 5.13.4-1 Core Average Hgap " Minimum"-*" Maximum" (see note) page 80, section 5.13
" Loss of Feedwater Flow"--*" Loss of Feedwater Flow Event" NOTE:
Discussions were implemented by the NRC staff during review of i
i the final methodology submitted. While it is the contention of the District that these are simply typographical errors, it is recognized that there is some concern. The Combustion Engineering transient methodology, which fonns the basis for the Districts methodology, states that the maximum value should be used in the event analysis indicated.
Additional information will also be forwarded to the staff under separate cover to assist in establishing l
the maximum Hgap value is correct.
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