ML20082E948
| ML20082E948 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/25/1991 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19302E926 | List: |
| References | |
| LIC-91-193R, NUDOCS 9108020201 | |
| Download: ML20082E948 (5) | |
Text
, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.s 1
=
Omaha Pubtle Power District J u..iy 25 1991 444 South 16th Street Mall L1C-91-193R Omaha, Nebraska G8102-2247 l
j 402/636-2000 V. S. Nuclear Regulatory Connission Attn: Document Control Desk Mail Station Pl-)37 Washington, D' M55
Reference:
1.
Docket No. 50 285 dated April 19,18{W. G. Gates) to NRC (Document Control Desk) 2.
Letter from OPPD OPPD NA 8302, Rev. 04(LIC 910126R) Analysis tiethodology 91 3.
" Reload Core Overview," April 1991 4s OPPD-NA 8303, Rev. 03 " Transient and Accident Methods and Verification," March 1991 Gentlemen:
SUBJECT:
Submittal of Westinghouse Mechanical Desiqn Reports WCAP-12977 (Proprietary) and WCAP-12978 IAonproprietary)
Omaha Public Power District (0 PPD) is enclosing twenty-three (23) ions of thecopies each of the proprietary (WCAP 12977 and nonproprietary Westinghouse Topic:1 Report) titled ' Westinghouse (WCAP-12978) versReload fuel Mechan Evaluation for the fort Calhoun Station Unit 1," dated June 1991.
These reports are to replace identically titled versions dated March 1991 submitted with Reference 2 which were not in the agreed upon format.
Please note that pursuant to 10 CFR 2.790, Westinghouse has determined that To)ical Report WCAP-12977 contains proprietary information to be withheld from pu)lic disclosure. Appropriate documentation justifying this determination is enclosed as is a revised reference page for each of the proprietary and nonproprietary versions of OPPD's Core Reload Topical Reports (References 3 and 4).
Revisions indicating the correct references are marked with a bar in the right margin.
If you should have any questions, please contact me.
Sincerely, N, b..
W. G. Gates Division Manager Nuclear Operations WGG/sel Enclosures l
c:
LeBoeuf, Lamb, Leiby & MacRae (w/o enclosures)
R. D. Martin, NRC Regional Admnnistrator, Region IV (w/o enclosures)
W. C. Walker, NRC Project Manager (w/o enclosures)
R. P. Mullikin, NRC Senior Resident inspector (w/o enclosures)
H. Borchert, Director - Division of Radiological Health, Nebraska Department of Health (w/o enclosures)
}
910eo3ok.[ Q ?M
"'R AD 3
c j
.La_qma wp
~mmy.
T
.s s.
I
- A 'l
l'.
}
i Proprietary Information Notice i
i Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in ccanection with requests for generic and/or plant-specific review and approval.
in order to conform to the requirements of 10 CTR 2.790 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been i
deleted in the non proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted).
The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower _ case letters (a) through (g) contained within parentheses located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information.
These lower case letters refer to the types of ir. formation Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(g) of the affidavit accompanying this tran?mittal pursuant to 10 CFR 2.790(b)(1).
1 l
~, -
-,,<--n-.
,-e-n -
rr-
-..,--,-n-
, + - - -,
an-v+
,-.ne-
,e---
en, e
Copyright Notice The reports transmitted herewith each bear a Westinghouse copyright notice.
The NRC is permitted to make the number cf copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, j
copyright protection not withstanding. With respect to the non proprietary versions of these-reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms
)
as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose.
The NRC is not authorized to make copies for the personal use of members cf the public who make use of the NRC pubile document rooms.
Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
I s-
l
8.0 REFERENCES
Section 2 References 2-1 WCAP-12977 " Westinghouse Reload Fuel Mechanical Design Evaluation for the Fort Calhoun Station Unit 1*, June 1991.
2-2
" Omaha Batch M Reload Fuel Design Report", CEN-347(0)-P Rev. 01, January 1987.
2-3
- Fuel Rod Maximum Allowable Gas Pressure", CEN-372-P-A, March 1990.
Sechon.1HeicIences 3-1
- Reload Core Analysis Methodology, Neutronics Design Methods and Venfication",
OPPD-NA-8302-P-A, Rev,02, April 1988.
E 3-2
- lNCA, Method of Analyzing incore Detector peta in Pressurized Water Reactors",
CENPD-145-P, April 1,1975.
3-3 Letter from R.W. Reid (NRC) to T.E.Short (OPPD), December 5,1978.
3-4 Letter from R.W. Rold (NRC) to W C. Jonec (OPPD). April 1,1980.
3-5
- lNCA/CECOR Power Peak Uncer1ainty", CENPD-153-P, Revision 1-P-A, May 1980.
3-6
- Statistical Combination of Uncertainties". CEN-257(0)-P-A, Parts 1 and 3, November g 1983.
Seguon 4 References 4-1
- CE Critical Heat Flux", CENPD-162-P-A Part 1, Combustion Engineering, September 1976.
4-2
- CE Critical Heat Flux", Part 2, CENPD-207-P-A, Combustion Engineering, June 1976.
4-3
A Computer Code for Determining the Thermal Margin of a Reactor Core "
CENPD-161-R TORC Code, Combustion Engineering, July 1975.
4-4 "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 & 2,"
CEN-191(B)-P, Combustion Engineering, December 1981.
4-5 Letter from Cecil Thomas (NRC) to Mr. A. E. Scherer (CE), November 2,1984.
OPPD-NA-8301-P, Rev. 04 Page 11 of 25
r
8.0 REFERENCES
S.ecuoB 2.HCiCLCBCCS 2-1 WCAP-12978 " Westinghouse Reload Fuel Mechanical Design Evaluation for the Fort Calhoun Station Unit 1". June 1991.
2-2
' Omaha Batch M Reload Fuel Design Report", CEN-347(0)-P, Rev. 01, January 19:31.
2-3
" Fuel Rod Maximum Allowablo Gas Pressure" CEN 372-P-A, March 1990.
Serlon 3 Reittentes 3-1
- Reload Coro Analysis Methodology, Noutronics Desig thods and Verification".
OPPD-NA-F a02-P-A, Rev. 02, April 1988.
E 32
" INCA, Method of Analyzing Incore Detector Data in Pressurized Water Reactors",
CENPD-145-P, April 1,1975.
3-3 Letter from R.W. Rold (NRC) to TE.Shor1 (OPPD), December 5,1978.
3-4 Letter from R.W. Rold (NRC) to W C. Jones (OPPD). April 1,1980.
3-5
- lNCA/CECOR Power Peak Uncertainty", CENPD-163-P, Pevision 1-P-A, May 1980.
3-6
Statistical Cambination of Uncertainties", CEN-257(0)-P-A. Parts 1 and 3, November g w83.
Section 4 References 4-1
- CE Critical Heat Flux", CENPD-162-P- A, Part 1, Combustion Engineenng, September 1976.
4-2 "CE Critical Heat Flux", Par 12, CENPD-207-P- A, Combustion Engineering, June 1976.
4-3
- A Computer Codo for Determining the Thermal Margin of a Reactor Core,"
CENPD--161-P, TORC Codo, Combustion Engineering, July 1975.
4-4
- CETOP-D Code Structure and Modeling Methods for Calvert Clifts Units 1 & 2."
CEN 191(B)-P, Combustion Engineering, December 1981.
4-5 Letter from Cecil Thomas (NRC) to Mr. A. E. Scherer (CE), November 2,1984 l
l l
l OPPD-NA-8301--NP, Rev. 04 Page 11 of 25