ML20011E252
| ML20011E252 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 01/29/1990 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19310C691 | List: |
| References | |
| NUDOCS 9002120365 | |
| Download: ML20011E252 (6) | |
Text
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,l Duke heer t'onwants '.
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- i'O Box 331% '. ! MMM-Thanotte, N C 28242 '
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! January 29, 1990 U..S. Nuclear Regulatory Commission Washington, D.C. -20555
~
. Attention: Document Control Desk
/Su)jpct: McGuire Nuclear Station-Docket Nos. 50-369, 50-370 Catawba Nuclear Station Docket Nos. 50-413', 50-414 "
Safety Analysis Physics-Parameters and Multidimensional Reactor Transients Methodology, DPC-NE-3001-P Gentlemen:
-Please find enclosed ~for your review fifteen copies of the proprietary Topical Report DPC-NE-3001-P, " Safety Analysis Phystics Parameters and-Multidimensional Reactor Transients Methodology." This report describes:thes
-Duke-Power Company methodologies for: (1) simulating the FSAR Chapter 15 events characterized by multidimensional reactor transients, and li) systematically confirming that reload physics parameters important to Chapter 15 transients and accidents are bounded'by values assumed in the licensing analyses. The multidimensional reactor transients described are the rod ejection accident, the main steam line break, and the dropped rod '
, Also, included are-four copies of three reports describing the EPRI computer ;
' code ARROTTA. This code is used in the analysis of the rod ejection.
~
g - O d( accident. The reports are: P los . -
ARROTTA: Advances Rapid Reactor Operational Transient Analysis:
4 Computer Code, Computer Code Documentation Package, Theory Manual.
Ro -
ARROTTA Validation and Verification - Standard Benchmark Set, EPRI M Research Project 1936-6, July 1989, Prepared .by S. Levy, Inc.
. In.y MO -
ARROTTA-HERMITE Code Comparison, EPRI NP-6614, December 1989.
28 .
.$ /The first report describes the theory incorporated into the computer
- g. software. The second provides validation and verification of the computer software to various numerical benchmarks. The third report provides
. ;*ogtt comparison of a rod ejection transient analyzed using ARROTTA to one analyzed using HERMITE which has already been reviewed and approved by the j NRC. These reports are included to facilitate review of the rod ejection l em . w w w a ,. w .*<
hk x ,. . ,{h** fa
l ,; i ' U. S. Nttelv.ir Regulctory Commiezion g January 19,s 1900
- Page 2; c
The' objectives of this report are to document the-methods to be used to verify: that the key physics parameters calculated- for a reload core are 9^ bounded by values assumed in the Licensing Chapter 15 analyses, and to describe the methods used to analyze three complex FSAR Chapter 15 accidents. Results of the multidimensional reactor transient analyses are presented to demonstrate the methods and to serve as substitute FSAR analyses.
'In accordance with 10CFR 2.790, Duke Power Company requests that this report be considered proprietary. Information supporting this request is included in the attached affidavit. A non proprietary version will be submitted following receipt of the Safety Evaluation Report.
If you hav'e any questions, or require more information, please call Scott Gewehr at (704) 373-7581.
Very truly yours,
( f l
Hal B.. Tucker SAG 206/lcs xc: (w/o Attachments)
Mr. Darl S. Hood, Project Manager Office of Nuclear Reactor Regulation-U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Kahtan Jabbour, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington,.D.C. 20555 Mr. S. D. Ebneter, Regional Administrator U. S.-Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900-Atlanta, Georgia 30323 Mr. Robert C. Jones, Acting Branch Chief Reactor Systems Branch Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 1
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p *' AFFIDAVIT OF TED C. McMEEKIN g , 1. I am Vice President, Design Engineering Department of Duke power Company- [n "~ (" Duke") and as such have the responsibility of reviewing the proprietary ,
.information sought to be withheld f :n. uuilic disclosure in connection ' +
with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding on behalfLof Duke. -!
.2. I am making this affidavit in conformance with the provisions of 10 CFR i; 52.790 of the regulations of the Nuclear Regulatory Commission ("NRC")
and in conjunction with Duke's application for withholding which accompanies this affidavit.
- 3. I have knowledge of the criteria used by Duke in designating information as proprietary or confidential.
- 4. pursuant to the provisions of paragraph (b)(4) of 10 CFR9 2.790, the following is furnished for consideration by the NRC in determining
- whether the information sought to be withheld from public disclosure should be withheld.
(1) The information-sought to be withheld from public disclosure is owned by Duke and has been held in coni'idence by Duke and its consultants. (ii) The information'is of a type that would customarily be held in - confidence'by Duke. The information. consists of analysis methodology details, analysis results, supporting data, and aspects of development programs,-relative to a method of analysis that-provides a competitive advantage to Duke. (a) The use of the information by a competitor would greatly reduce its expenditure in qualifying similar methodologies. t (b) It reveals aspects of a methodology with potential commercial value to Duke power. (iii) The information was transmitted to the NRC in confidence and under I the provisions of 10 CFR 2.790, it is to be received in confidence by the NRC. (iv) The information sought to be protected is not available in public sources to the best of our knowledge and belief. Ted C. McMeekin j (continued)
y s 4 h. F r
' AFFIDAVIT OF TED C. McMEEKIN (Page 2) k h (v)' The proprietary information sought-to be withheld in this submittal-it is1that which is marked in the proprietary version of the report f #
DpC-NE-3001-p, Safety Analysis physics parameters ai.d [' Multidimensional Reactor Transients Methodology, and omitted from the non-proprietary version. This'information enables Duke to: (a) ' Systematically confirm that reload physics parameters important to FSAR Chapter 15 transients and accidents are bounded by values assumed in the licensing analyses, f (b) Simulate the following Chapter 15 events: the rod j ejectica accident, the main steam line break, and the droppid rod transient. (vi)l The proprietary information sought to be withheld from p.iblic disclosure has substantial commercial value to Duke. .; i (a) -It allows Duke to reduce vendor and-concultant expenses associated with supporting the operation and licensing of nuclear power plants. (b) Duke intends to sell the information to nuclear utilities, vendors, and consultants for the purpose of supporting the operation and licensing of nuclear power plants. (c)' The subject information could only be duplicated by. competitors at similar expense to that incurred by Duke.
- 5. Public disclosure of this information is likely to cause harm to the-position of Duke because it-would allow competitors in the nuclear j '
industry to benefit from the results of a significant development program without requiring a commensurate expense or allowing Duke to recoup a portion of its expenditures or benefit from the sale of the-information.
)
f i l,
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k?!) Mil Ted C. McMeekin l (continued) J
g" w -, x . ,y , f.i , b pL
*; 4 :
7, ;;, -*s [t '. . .. . y?- b k. AFFIDAVIT OF TED C. McMEEKIN (Page 3) fl, ' y; p c?ed C. McHeekin, being duly aworn, on his-oath aeposes and says that he=is the-k: person who subscribed his name to'the foregoing statement, and that the f? matters and fucs cet forth in the statement are true. 6 Ted C. McMeekin i!.
-Sworn to and subscribed before me-this /f day of b//h/4 , 1990.
Witness my hand and official seal.. / / i
$ )- h /$ L ugtergeunuc g e ~ s1ssio,, e e - p w a m l
It ' t k s J u l I 4 1 4
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