ML20082D837
| ML20082D837 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/11/1983 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19274C105 | List: |
| References | |
| LIC-83-283, NUDOCS 8311230076 | |
| Download: ML20082D837 (4) | |
Text
Il cv.
Omaha Public Power District 1623 Harney Omaha Nebraska 68102 402/536 4000 November 11, 1983 LIC-83-283 Mr. James R. Miller, Chief U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.
20555
Reference:
Docket No. 50-285
Dear Mr. Miller:
Subject:
Submittal of Statistical Combination of Uncertainties Reports in Support of the Fort Calhoun Station Cycle 9 Reload Submittal Omaha Public Power District's letter of July 28, 1983 discussed the fact that the District intended to use a Statistical Combination of Uncertain-ties (SCU) in the Cycle 9 reload analysis. The SCU analysis was performed by Combustion Engineering utilizing the methodology previously submitted and approved on the Calvert Cliffs and St. Lucie dockets. Enclosed are the necessary proprietary and non-proprietary versions of the SCU reports.
This letter also transmits a revision to OPPD-NA-8301 and to OPPD-NA-8303.
The revisions properly incorporate the SCU reports into the list of references in the District's methodology reports.
Please note that pursuant to 10 CFR 2.790(b)(1), certain portions of the enclosed information has been deemed trade secrets and/or privileged commercial information by Combustion Engineering, Inc. (CE). Accordingly, please find enclosed the District's application for withholding this information from public disclosure, as well as CE's affidavit in support of the application.
l Sincerely, YkV k6 ld
{
W. C. U nes
,{5 lJ I
Divisi'o Manager Production Operations I
WCJ/JKG/1p
.N
[
g
}
Enclosures 08
'E g
cc:
LeBoeuf, Lamb, Leiby & MacRae Mr. E. G. Tourigny, Project Manager Mr. L. A. Yandell, Senior Resident Inspector Sh$a 0$$00 Employment h a al opporttmity
[A
4.
BEFORE THE UNITFD STATES NUCLEAR REGULATORY COMMISSION In the Matters 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 disclosure. Applicant has been informed by Combustion Engineering, Inc. (CE) that this information is owned by CE and that in the opinion of CE the information in question contains trade secrets and/or privileged or confidential commercial or financial information.
An attached affidavit executed by CE identifies the documents sought to be withheld and sets forth the bases on which the information may be withheld from public disclosure by the Commission. The affidavit also j
addresses the considerations listed in Pargraph (b)(4) of Section 2.790 with specificity.
Respectfully submitted, i
l OMAHA PUBLIC POWER DISTRICT By i
(Y/ W W.
C'.' Jones l
Divi ls' ion Manager l
Production Operations I
Sworn to before me on this
/f7g day of devemgfg
, 1983 kbm/D f
Notary Public eauem usinar-sm. e me.m J.T.GLEASON Mr Coma to July 28. HIS L
fl
.~
7.0 REFERENCES
(Continued) 7.
" Statistical Combination of Uncertainties," CEN-257(0)-P, Parts 1 and 3, November 1983.
8.
"CE Critical Heat Flux," CENPD-162-P-A, Part 1, Combustion Engineering, September 1976.
9.
"CE Critical Heat Flux," Part 2, CENPD-207-P-A, Combustion Engineering, June 1976 10.
"A Computer Code for Determining the Thermal Margin of a Reactor Core," CENPD-161-P, TORC Code, Combustion Engineering, July 1975.
11.
"CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 A 2," CEN-191(B)-P, Combustion Engineering, December 1981.
12.
Letter from R. A. Clark (NRC) to W. C. Jones (OPPD),
March 15, 1983.
13.
Letter from W. C. Jones (0 PPD) to R. W. Reid (NRC),
December 4,1979.
14.
" Statistical Combination of Uncertainties," CEN-257(0)-P, Part 2, November 1983.
i 15.
"Peload Core Analysis Methodology, Transient and Accident Analysis Methais and Verification," 0 PPD-NA-8303, September 1983.
16.
"CE Setpoint Methodology," CENPD-199-P, Revision 1-P, April 1982.
i l
I 13 OPPD-NA-8301 11/83
r
.o
7.0 REFERENCES
(Continued)
Section 4 References 4-17 CEN-257(0)-P, " Statistical Combination of Uncertainties",
November, 1983.
Section 5 References 5-1 CEN-121(B)-P, "CEAW, Method of Analyzing Sequential Control Element Assentily Group Withdrawal Event for Analog Protected Systems", November,1979.
5-2 CENPD-199-P, Revision 1-P, "CE Setpoint Methodology", April, 1982.
5-3 Letter from W. C. Jones to R. A. Clark, LIC-83-157, dated June 30, 1983.
5-4 Fort Calhoun SER on Automatic Initiation of Auxiliary Feedwater, contained in the letter to W. C. Jone from Robert A. Clark, dated February 20, 1981.
5-5 XN-NF-78-44, "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors", January,1979.
5-6 OPPD-NA-8302, " Nuclear Design Methods and Verifications",
Sep tember, 1983.
Section 6 References 6-1 "CESEC - Digital Simulation of a CE NSSS," Enclosure 1-P to LO-82-001, January 6,1982.
l 118 OPPD-NA-8303 11/83