ML20009A109
| ML20009A109 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/17/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 8107080408 | |
| Download: ML20009A109 (3) | |
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Docket File 50-382 LPDR JKnight JUN 17 1981 PDR
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WJohnston NSIC DMuller TERA PCheck Docket No.:
50-382 LB#3 Files WKreger DEisenhut LRubenstein RPurple FSchroeder Mr. D. L. Aswell SHanauer MErnst Vice President, Power Production TMurley FMiraglia RMattson ASchwencer Louisiana Power & Light Company 142 Delaronde Street RVollmer BJYoungblood New Orleans, Louisiana 70174 SBlack JRMiller JLee EAdensam TNovak RHartfield, MPA
Dear Mr. Aswell:
GLainas ELD
SUBJECT:
REQUEST F0P, ADDITIONAL INFORMATION - VATERFORD 3 IE (3)
ACRS (16)
We have determined that certain additional information is required in order to permit us to complete cur review of your application for an operating license for Waterford Stean Electric Station, Unit 3.
The enclosed round two requests for additional information were prepared by the Core Performance Branch and are numbered 221.17 through 221.19.
Please advise us of the date you expect to provide responses to the enclosed request. If you require any clarification, please contact the staff's assigned project manager.
Sincerely, 0%Inal signed by Robert,1,,, Tedesen Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosure:
Request for Additional
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50-382 Mr. D. L. Aswell Vice President, Power Production Louisiana Power & Light Company 142 Delaronde Street New Orleans, Louisiana 70174
Dear Mr. Aswell:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - WATERFORD 3 We have determined that certain additional information is required in order to permit us to complete our review of your application for an operating license for Waterford Steam Electric Station, Unit 3.
The enclosed round two requests for additional information were prepared by the Core Performance Branch and are numbered 221.17 through 221.19.
Please advise us of the date you expect to provide responses to the enclosed request. If ycu require any clarification, please contact the staff's assigned project manager.
Sincerely, D?.b.-'E.m Robert L. Tedesco3 Assistant Director for Licensing Division of Licensing
Enclosure:
Request for Additional Information cc w/ encl: See next page.
O
j i rir. D. L. Aswell UATERFORD Vice Pr.asident, Power Production Louisiana Power & Light Company 142 Delaronde Street New Orleans, Louisiana 70174 W.11alcolm Stevenson, Esq.
Monree & Lemann 1424 Uhitney Building New Orleans, Louisiana 70130 Mr. E. Blake Shaw, Pittman, Potts and Trewbridge 1800 M Street, N. W.
Washington, D.C.
20036 Mr. D. B. Lester Production Engineer Louisiana Power & Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Lyman L. Jones, Jr., Esq.
Gillespie & Jones P. O. Box 9216 Metairie, Louisiana 70005 Luke Fontana, Esq.
Gillespie & Jones 824 Esplanade Ave.
New Orleans, Louisiana 70116 Stephen M. Irving, Esq.
535 North 6th Street Baton Rouge, Louisiana 70802 Resident Inspector /Waterford NPS P. O. Box 822 Killona, Louisiana 70066 Dr. Krishna R. Iyengar Middle South Services, Inc.
P. O. Box 61000 New Orleans, Louisiana 70161 i
221.0 Thermal Hydraulics Section/ Core Performance Brancn 221.17 Standard format and centent of Safety Analysis Reports, Regu-latory Guide 1.70, states that in Chapter 4 of the SAR
...the applicant should provide an evaluation and sup-porting infornation to establish the capability of the reactor to perform its safety functions throuchout its design lifetime under all normal operation modes..."
Are the analyses presented in Section 4.4 representative of.
ths initial core cnly or have future cycles been analyzed?
Provide a discussion of how power distributions for future cycles are considered in the FSAR analyses.
Is there any assurance that Waterford-3 can operate at the licensed power level without excessive DNB trips throughout future cycles?
Will revisions to the design methodology be recuired in order to maintain sufficient thermal margin?
221.18 In Amendment 18 to the Waterford-3 FSAR the grid design was changed from a C-E standard grids to High Impact Design (HID-
- 1) grias ar.2 tne center-to-center grid spacing was changed frc 14.2 inches to 15.7 inches.
The CE-1 CHF correlation was based on test data having grid spacings of 14.3 inches,17.4 inches, and 18.25 inches and using C-E standard grids.
Justify using the CE-1 correlation for the new Waterford-3 fuel design.
221.19 A change in grids will result in a change in diversion cross-flow between assemblies.
For the TORC analyses, what were the values used for the turbulent mixing factor and the diversion cross flow factor and what effect do the different spacer crids have on turbulent mixino and diversion cross flow?
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41so, supply the minimum D.';3R at nominal conditions for the new fuel design.
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