ML17046A335

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Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.2-1 to 4.2-2
ML17046A335
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/30/2017
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17046A230 List: ... further results
References
LR-N17-0034
Download: ML17046A335 (2)


Text

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  • TABLE 4.2-1 MAXIMUM DEFLECTIONS ALLOWED FOR REACTOR INTERNAL SUPPORT STRUCTURES Component Upper Barrel radial inward radial outward Upper Package Rod Cluster Guide Tubes SGS-UFSAR Allowable Deflections (in.) 4.1 0.5 0.10 1.00 1 of 1 No-Loss-of-Function Deflections (in.) 8.2 1.0 0.15 1. 75 Revision 6 February 15, 1987 TABLE 4.2-2 COMPARISON OF SINGLE AND DOUBLE ENCAPSULATED SECONDARY SOURCE DESIGNS PA.RAMETE:R Number of rodlets Outer Clad OD, in. Outer Clad ID, in. Inner Clad OD, in. Inner Clad ID, in. Pellet OD, in. Pellet Stack Length, in. Pellet Stack Weight, grams Sp=in; Clip Material Outer psig Inner psig ., SGS-UFSAR SINGLE ENCAPSULA'J:ED 4 0.361 +I-0.001 0.344 +!-0.0005 N/A N/A 0.338 +0.002/-0.001 88.00 500/535 Carbon steel -plated 625 +/-50 N/A 1 of 1 DOUBLE ENCAPSt.T.LATED 6 0.381 +I-0.001 0.344 +I-0.0005 b.344 +I-0.001 0.297 +I-0.0005 0.292 +/-0.001 86.00 338 +/-10 410 Stainless steel 625 +/-50 250 +/-20 Revision 18 April 26, 2000