ML20098F123
| ML20098F123 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/26/1984 |
| From: | Ellis J Citizens Association for Sound Energy |
| To: | Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel |
| References | |
| CON-#484-150 OL-2, NUDOCS 8410020356 | |
| Download: ML20098F123 (1) | |
Text
f C A S E==
(CITIZENS ASSN. FOR SOUND ENERGY)
. -[
n?:r:
g September 26, 1984 Administrative Judge Peter B. Bloch Dr. Kenneth A. McCollom, Dean -
U. S. Nuclear Regulatory Ccmmission Division of Engineering, Architecture 4350 East / West Highway, 4th Floor and Technology Bethesda, Maryland 20014 Oklahoma State University Stillwater, Oklahoma 74074 Dr. Walter H. Jordan 881 W. Guter Drive Oak Ridge, Tennessee 37830 Gentlemen:
SUBJECT:
In the Matter of Application of Texas Utilities s
F Generating Company, et al. for An Operating License for Comanche Peak Steam Electric Station Units #1 and #2 (CPSES)
Docket Nos. 50-445 and 50-446 CL Board's 9/17/84 Memorandum and Order (Directing Release of 01 Reports)
CASE is in complete agreement with the Board's subject Order, with one minor exception. The Board has stated (page 5):
"The Board is willing to limit those included in the protective order to two legal representatives for each party... "
If the Board does indeed make such limitation, CASE must designate myself and Mr. Roisman as those two representatives. However, we believe because of the unusual circumstances wherein we are separated not only by distance but by the press of working on different things at different times, it would be far preferable and would in no way increase the number of individuals so designated to the point of jeopardizing the level of confidentiality for Ms. Garde to also be included, and we request that the Board allow CASE three representatives in this unusual instance.
Otherwise, as stated in the preceding, CASE designates myself and Mr. Roisman as the two representatives.
Respectfully submitted, CASE (Citizens Association for Sound Energy) 8410020356 840926
,g u M,v h w '
PDR ADOCK 05000445 O
PDR Mrs.) Juanita Ellis President cc:
Service List 50 3
Babcock & Wilcox utere a.n-.n o w.n a McDermott company 3315 old Forest Road P.O. Box 126o Lyncht urg, VA 245051260 (So4)385-2000 September 26, 1984 Mr. Cecil 0. Thomas, Chief Standardization and Special Projects Branch Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Thomas:
We have recently received your letters concer(ning acceptance for referencing of the topical reports BAW-10129 l? and BAW-10130(2)
(LYNX 1 and LYNX 2 Codes). Both letters state that, "We have concluded that the combination LYNX-1 providing bundle boundary conditions for the LYNX-2 subchannel code (two-pass analysis) is an acceptable method for evaluating DNBR margins when used in licensing calculations with NRC approved CHF correlations.
The BWC correlation currently used by B&W is acceptable for the purpose."
The purpose of this letter is to note that B&W-2(3) is also an NRC approved CHF correlation and that B&W-2 is currently used by B&W for evaluating DNBR margins in reactor cores which utilize our 15x15 Mark-B fuel assembly design.
The use of B&W-2, in the two-pass LYNX 1/ LYNX 2 analysis, is an appropriate method of evaluating DNBR margins as demonstrated by the following:
a) Reference 4 provides a comparative analysis which demonstrates that the use of B&W-2 is appropriate for DNBR evaluations using the LYNXT(3) code.
b) References 5 and 6 provide comparative analyses which demonstrate that LYNX 2 and LYNXT are equivalent when used for DNBR calculations.
Since B&W-2 is an NRC-approved CHF correlation and has been shown to be appropriate for use in crossflow analyses, we consider the acceptance of LYNX 1/ LYNX 2 for DNBR margin evaluations to encompass the use of B&W-2 as well as BWC.
As a matter of clarification we plan to include this letter in the accepted versions of the LYNX 1 and LYNX 2 topical reports.
Should you need any further information concerning this subject, please contact Mr. C. F. McPhatter at (804) 385-2401.
ruly
- urs, 8410020369 840926 b
di PDR TOPRP EMVBW J. H. T y o I
C PDR Manager, L censing JHT/lec
E l
. References 1.
Letter, Cecil 0. Thomas to J. H. Taylor, Acceptance for Referencing of Licensing Topical Report BAW-10129, " LYNX 1 - Reactor Fuel Assembly Thermal Hydraulic Analysis Code," August 23, 1984.
2.
Letter, Cecil 0. Thomas to J. H. Taylor, Acceptance for Referencing of Licensing Topical Report BAW-10130, " LYNX 2 - Subchannel Thermal-Hydraulic Analysis Program," August 23, 1984.
3.
" Correlation of Critical Heat Flux in a Bundle Cooled By Pressurized Water," BAW-10000A, Babcock & Wilcox, Lynchburg, VA, May 1976.
4.
Letter, J. H. Taylor to Cecil 0. Thomas, August 27, 1984.
5.
R. L. Harne/J. H. Jones, " Thermal-Hydraulic Crossflow Applications,"
BAW-1829, Babcock & Wilcox, April 1984.
6.
Letter, J. H. Taylor to Cecil 0. Thomas, " Request Number One for
-Additional Information - BAW-10156, May 4, 1984," July 2, 1984, cc:
R. B. Borsum (B&W)
G.
Schwenk (NRC) f l
1
)
-