ML19329D760
| ML19329D760 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/04/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Darrin Butler Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003170702 | |
| Download: ML19329D760 (4) | |
Text
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NRC pow 195 u.s. NUCLLan nEcVLAtony Couu SstCN DOCKET NUMIE R 50-302 NRC Dic.'RidUTION rOn PART 50 DOCKET MATERIAL l70:
D. A. Butler FROM:Flordia Power Corp.
DATE OF DOCUMENT St. Petersburg, Flordia 5-4-76 J.T. Rodgers oATE nECEivEo
. 7-76 OLETTEn O NOTon12E D P rtOP INPUT FOP *4 NUMsER OF COPIES nECEIVED SoniclNAL DONCLASSIFIE D i
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l oEsCnsPTION ENCLOSunE Ltr. trans the following.......
Introduction of Clad-Creep-Collapse Analysis.
(3 Originals Re*ceived)
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l PLANT NAME:
Crystal River # 3 n..- --
SAFETY FOR ACTION /INFORMATION ENVIRO e
. ASSIGNED AD :
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BRANCH CHICF :
Butler BRANCH CHIEF :
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Butler, Chief (f
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Director of Nuclear Reactor Regulation 4'Q,&%i[S
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U.S. Nuclear Regulatory Commission 9
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Washington, D. C.
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'e In Re:
Florida Power Corporation i
G Crystal River Unit #3
, Docket No. 50-302
Dear Dr. Butler:
Supplementing the report on our replacement Fuel Assembly 3A33 dated 3/26/76, we are forwarding to you the attached two pages titled, " Introduction".
With this submittal, we will have supplied all information requested of us or BGW on this subject for your review and acceptance.
We have been verbally so informed of your acceptance and all necessary clearances have been obtained leading to shipment of this element to Crystal River this week.
Very truly yours,
/.
J. T. Rodgers Asst. Vice President JTR/iw Attachments.
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General Office 3201 Thirty-fourtn street soutn. P O Box 14042. St Petersburg Floncia 33733 813 - 866-5151
6 INTRODUCTION The following information further describes the clad creep-collapse and fuel 1
clad interaction evaluations referenced in the Mechanical Section of the Report on Replacement Fuel Assembly 3A33, dated March 26, 1976.
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Clad Creep-Collapse Analysis The clad creep-collapse analysis was performed in accordance with material properties and design procedures set forth in Topical Report BAW-30084P-A, entitled. " Program to Determine In-Reactor Performance of B&W Fueli'. The evaluation was comple'ted using the NRC approved CROV creep ovalization analysis code as described in Section 3. of the above referenced report.
In addition, the following input conservatisms were introduced:
1.
The fuel rod is assumed to contain only 90.9 % TD fuel.
This decreases the prepressure level due to densification.
2.
The minimum specification prepressure level is used.
3.
The mean plus 2a cladding ovality and mean minus 2a cladding thickness were used, as determined from manufacturing as-built dimensions.
Results of the analysis indicate a time to collapse >14,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. This is sufficiently greater than the required 10,320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> associated with the single cycle burn of assembly 3A33.
Fuel Clad-Interaction Analysis The fuel-clad interaction and fuel swelling affects are addressed in the clad strain analysis. Of the pellet densities used in assembly 3A33, the slightly larger nominal diameter, 90.9% TD pellets represent the limiting fuel clad interaction case at the peak pellet burnup seen by the assembly.
(22,600 MiD/MIU with uncertainty included.) This is consistent with the fact that the peak pellet burnup is less than the transition from the 0.16% aV/V/ 1020f/cc rate for the other pellet designs of this assembly.
(See Table 1 of the March 26th Report.)
. Accordingly, clad strain analyses were performed on the 90.9% TD fuel corres-ponding to the worst-case specification dimensions and the as-bui.lt, two sigma dimensions.
sa The andlyses were performed in accordance with material data and design models set forth in Section 3 of Topical Report BAW-10054, Revision 2, entitled " Fuel Densification Report". This represents the same approach as used in the Crystal Rive' r SAR analysis except that the following additional conservatisms were intro-duced for the 3A33 analyses:
1.
Input pellet diameter was set as the nominal OD plus tolerance value (worst case specification analysis).
2.
Input clad ID was set as the nominal ID minus tolerance value (worst case specification analysis).
3.
Input pellet diameter was set as the mean OD plus the 2a value
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(as-built analysis).
4.
Input clad ID was set as the mean ID minus the 2a value (as-built analysis).
The results of the above analyses indicate that the total circumferential strain resulting fron fuel clad interaction for the worst-case-specification analysis cnd the as-built dimensions analysis are 0.80% and 0.48% respectively.
This is well below the allowable value of 1.42%.
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