ML19220C399
| ML19220C399 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/13/1974 |
| From: | Ross D US Atomic Energy Commission (AEC) |
| To: | Kniel K US Atomic Energy Commission (AEC) |
| References | |
| NUDOCS 7905010122 | |
| Download: ML19220C399 (3) | |
Text
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',e UNITED STATES ATOMIC ENERGY COMMISSION b
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wAsmsoros. o c. zos4s na Dccket No.
50-320 K. Kniel, Chief, Lignt Water Reactors Branch No. 2-2,L ACCEPTANCE REVIEW CN THREE MILE ISLAND UNIT 2 Plant Name:
Three Mile Island Unit 2 Licensing Stage:
CL Docket No.-
50-320 Responsible Branch LWR 2-2 and Project Manager:
B. Washburn Tecnnical Rev.iew Branch Involved:
Core Performance Branch Requested Ccmpletion Date:
March 5, 1974 Section 4.2.1 All pertinent information required for a review is cresent with tne exception of dimensions and tolerances, some of which in the past have been considered prcprietary. These can be obtained in 01 questions.
Therefore, Section 4.2.1 is capable of being reviewed.
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O. F. Ross, Chief Core Performance Branch Directorate of Licensing Attachment cc:
S. Hanauer J. Hendrie A. Giambusso W. Mcdonald V. Stello R. Boyd RP ads TR ads TR Technical Coordinators RS SCs R. 10 bel B. Washburn L. Rubenstein S. Varga 33 357 790E01ol.22 M
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MINI-RIV!E'4 THREE MILE ISLUQ CNIT 2 Se: tion 4.2.1oftheFSARforThree$[le Island, Unit 2, has beer, reviewed to see if the proper information has been included so that it :an be rcviewed.
This was done by a cross check between Section e.2.1 cf the FSAR and the" Standard For=at and Content of Safety Analysis Reports for Nuclear Power Plants (Revision 1)" issued by the Regulatory Staf f in October, 1972.
The purpose of Section 4.2.1.1 is to explain and substantiate the design bases used in the fuel design. The applicant gave the following consideraticas in h'.s discussion of design bases as an outline in the Standard Format referenced above:
(1) physical properties (2) stress strain limits (3) effects of fu21 swelling (4) variations in nelting point and thermal conductivity Specific numbers and curves were given for the above considerations so that the applicant, in Secticn 4.2.1.1 appears to be in compliance with the Stantard For=at.
Section 4.2.1.2 must contain final design drawings of fuel assemblies showing arrange =ent, dimensions, critical tolerances, sealing and handling features, nethods of supports, fission gas spaces, burnable poison content, and the internal components.
It does not appear that the applicant has included all this infor ation.
There are no di=ensions whatsoever on the drawing. The test has no centien of critical tolerances such as fuel pellet diameter and cladding inner dianeter tolerances, cladding ovality, wall thickness and fuel pellet density
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. Section 4.2.1.3 deals with design evaluation, i.e.,
including effects of normal and transient reactor conditions. The description of these ef fects is adequate to do a review.
Section 4.2.1.4, dealing with testing and inspection plan is also acceptable for review.
In suumary, Section 4.2.1 has been evaluated as acceptable for review with the exception of some details in fuel red tolerances.
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