ML19260C462
| ML19260C462 | |
| Person / Time | |
|---|---|
| Issue date: | 04/04/1978 |
| From: | Ross D Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19260C458 | List: |
| References | |
| REF-GTECI-A-02, REF-GTECI-RV NUDOCS 8001030526 | |
| Download: ML19260C462 (2) | |
Text
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b UNITED ST ATES l --
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o NUCLEAR REGULATORY COMMISSION
.e' WASHINGTON, D. C. 20555 i
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%.,$fMORANDUMFOR:
APR 4 1978 D. B. Vassallo, Assistant Director for Light Water Reactors, DPM FROM:
D. F. Ross, Jr.., Assistant Director for Reactor Safety, DSS SUBJ ECT:
ACCEPTANCE REVIEW 0F BABC0CK AND WILC0X LICENSING TOPICAL REPORT, BAWa10133
REFERENCE:
Letter from S. A. Varga to R. J. Mattson, Nov. 14, 1977.
We have performed a cursory review of BAW-10133, Mark C Fuel Assembly-LOCAaSeismic Analysis," October 18, 1977, and find that it does not contain sufficient information for us to begin a meaningful detailed review.
We, therefore, request that you notify B&W that a revision to the present report is needed to provide substantially more technical information. The following items illustrate the types of information we need:
- 1) Physical dimensions and weights of the components of the fuel assembly.
- 2) Material properties, including Young's modulus, yield stress, Poison ratio, ultimate stress.
- 3) Design limits in terms of specific stress, strain, deflection and grid crushing load.
4)
Input forcing functions for the Seismic and LOCA loads (hp history on fuel) including corresponding core plate motions.
- 5) Analytical results given in quantitative values in tems of stress, strain, deflection and grid crushing load, including corresponding safety factors.
A
- 6) Detailed description of the experiments used to obtain physical and analytical parameters such as impact spring constant of grid, damping and stiffness.
7)
Specific values used in the computer analysis input.
1700 115
Contact:
S. Kim, x27603 sce1oso
D. B. Vassallo gg 4 *, /g g
- 8) Verification tests for the computer calculation which include the multi fuel assembly impact. Comparisons with academic text book problems and simple non-representative tests alone are not sufficient.
Upon receiving a revised report, we will schedule it for review. We expect that the total calendar time required for the review will be approximately one year.
' Lam 0 wN Denwood F. Ross, Jr.g Assi tant Director for Reactor Safety Division of Systems Safety cc:
J. Wilson B. Saffell, INEL B. Grubb, INEL S. Hosford M. Tokar D. Ross R. Mattson x
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