ML20094C032
| ML20094C032 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/31/1984 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8408070348 | |
| Download: ML20094C032 (3) | |
Text
o NUOIME GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054-1149 (201) 2r3-6500 TELEX 136-482 Wnter's Direct Dial Number:
July 31, 1984 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Spent Fuel Pool Expansion By GPU Nuclear letter dated September 2,1933, I submitted Facility Description and Safety Analysis Report Amendment No. 79, " Licensing Report on High-Denrity Spent Fuel Racks for Oyster Creek Nuclear Generating Station,"
dated August 1983. As a result of a meeting with your staff in Bethesda, Maryland on April 16, 1984, it was agreed that several pages of our September 2, 1983 submittal needed to be revised for clarification purposes.
The enclosed attachments, pages 6-17 and 6-18, have been revised and should be used to replace those similar pages in the August 1983 document.
Very truly yours, y-
. m. tiedler Vice President and Director Oyster Creek Ir/0285e cc: Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N. J.
08731 8408070348 840731 PDR ADOCK 05000219 P
\\
\\
GPU Nuclear Corporation is a sutmdiary of General Pubhc Utiht:es Corporation L
.It should be noted that in the numerical simulations run to verify structural integrity during a seismic event all elements of the fuel assemblies are assumed to move in phase.
This will provide maximum impact force level, and hence induce additional conservatism in the time history analysis.
This equation set is mass uncoupled, displacement coupled, and is-ideally suited for numerical solution using the central difference scheme.
The computer program named "DYNAHISat, developed by General Electric Company, performs this task in an efficient manner.
Having determined the internal forces as a function of time, the computer program "EGELAST" computes the detailed stress and displacement fields for the rack structure as described in the preceding section.
6.5 Structural Acceptance Criteria There are two sets of criteria to be satisfied by the rack modules:
(a) Kinematic Criterion:
This criterion _ seeks to ensure that' adjacent racks. will not impact during SSE
-(condition E'14) or OBE conditions for any admissible value of liner / rack interface friction coef ficient. It is further required that the factors of safety against tiltingl5 are met (1.5 for OBE, 1.1 for SSE).
(b) Stress Limitis (1) The stress limits of the ASME Code,Section III,
~ Subsection NF, :1980 Edition are required to be met, l since t This code has been previously utilized in licensing of similar racks for Fermi II (Docket No.
50-341),
Quad Cities I and II (Docket Nos. 50-254 and 265), and Rancho Seco (Docket No. 50-312).
6-17
~_
f this Code provides the most consistent set of limits for various stress types, and various loading conditions.
The following loading casesl4 have been analyzed.
Loading Combination Stress Limit D + L + To + E Meet the stress limits of the ASME Code Section III Normal condition (Level A)
D + L + Ta + E' Meet the stress limits of the U
ASME Code Section III Faulted Condition (Level 0) where D=
Dead weight induced stresses L=-
Live load induced stresses; in this case stresses are developed during lifting.
The above two stress limits boun.d all loading cases specified in the OT Position for Review and Acceptance of Spent Fuel Storage s
and Handling' Applications.
The conditions Ta and To cause local thermal stresses to"
-be produced.
The worst situation will be obtained when an isolated'
~
storage location has'a fuel assembly which is generating heat at' the maximum postulated rate.
The' surrounding storage locations are assumed to contain no fuel.
Furthermore, the loaded storage location is assumed to have unchanneled fuel.
Thus, the heated water makes unobstructed contact with' the inside of the storage t
' walls, thereby producing maximum possible ' temperature difference
.between the adjacent cells.
The secondary stresses thus produced are limited to the body of the rack; that is, the support legs do
.not experience the secondar'y (thermal) stresses.
- S s Yield stress of the material; s s ultimate stress.
y u
6-18
-.. -