ML20032C626

CEN-187(L)-NP, Preliminary Assessment of St Lucie 2 Fuel Structural Integrity Under Faulted Conditions

ML20032C626
Person / Time
Site:	Saint Lucie
Issue date:	10/23/1981
From:	ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
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ML17212A983	List: L-81-471, Forwards Proprietary & Nonproprietary Preliminary Assessment of St Lucie 2 Fuel Structural Integrity Under Faulted Conditions. Affidavit for Withholding Encl ML20032C626
References
CEN-187(L)-NP, NUDOCS 8111100664
Download: ML20032C626 (16)

Text

ST. LUCIE-2 i'

DOCKET 50-389 CEN-187(L)-NP PRELIMINARY ASSESSMENT OF

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ST. LUCIE-2 FUEL STRUCTURAL !!iTEGRITY UNDER FAULTED CONDITIONS OCTOBER 23, 1981 e

COMBUSTION ENGINEERING, INC.

NUCLEAR POWER SYSTEMS POWER SYSTEMS GROUP WINDSOR, CONNECTICUT 06095 lbh [$0h 0$0 A

LEGAL NOTICE This report was prepared as an account of work sponsored by Combustion Engineering Inc.

Neither Combustion Engineering nor any person acting on its behalf:

A.

Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefullness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or B.

Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method or process disclosed in this report.

1 9

. INTRODUCTION This document formally transmits the preliminary assessment of the St. Lucie-2 fuel structural integrity under faulted conditions.

The contents of this document are similar to Reference (1) presented on'the Waterford-3 docket.

The seismic analysis methods and models presented utilize the methodology of the C-E fuel topical report, CENPD-178 (Ref. 2).

The LOCA analysis methods and models represent an initial improvement over the LOCA methodology in CENPD-178, and are essentially based on the fuel seismic models from the topical report. These results represent the best information for St. Lucie-2 availa~ le o

at this time.

The final assessment of the St. Lucie-2 fuel structural integrity under seismic and LOCA loadings will be provided in May 1982.

The final assessment wil!

utilize the recently developed methods and models presented in CENPD-178 - Rev.1 (Ref. 3).

9 Ref. 1 - CEN-159(C).P, ' Preliminary Assessment of Waterford-3 Fuel Structural Integrity Under Faulted Conditions", C-E Proprietary Report, May 4,1981 Ref. 2 - CENPD-178, " Structural Analysis of Fuel Assemblies for Combined Seismic and Loss of Coolant Accident Loading", C-E Proprietary Report, August 1976 Ref. 3 - CENPD-178 Rev. 1, " Structural Analysis of Fuel Assemblies for Seismic and Loss of Coolant Accident Loading", C-E Proprietary Report, August 1981

2-a PRELIMINARY SEISMIC ANALYSIS OF FUEL The preliminary seismic analysis of the St. Lucie-2 fuel assemblies was performed by the procedure outlined in CENPD-178 (Ref. 2).

In the first step of the pro-cedure, input excitation to be used for the reactor internals plus core was developed. This consisted of the horizontal, vertical and rotational (rocking) time history responses of the reactor vessel aetermined from the reactor coolant system seismic analyris.

Next, this excitation was input into separate horizoatal and vertical models af the reactor internals plus core.

For the horizontal direction, the analysis of the coupled internals and core yielded the time history responses of the core plates and the core shroud.

The responses of the core plates and the core sh:oud vere input into a detailed core model representing the longest row across the core (.17 fuel assemblies).

For the vertical direction, the core response was obtained directly from the coupled internals pits core analyses.

The results of +he St. Lucie-2 core preliminary seismic analysis are shown on Figures 1 aim z.

They consist of peak one-sided and through-grid spacer grid impact loads for the Safe Shutdown Earthquake (SST.).

These results are for the longest row across the core.

h l

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, PRELIMINARY LOCA ANALYSIS OF FUEL Structural analyses of the St.2Lucie-2 reactor coolant systera were performed for afullpowerposgulated200in guillotine break at the reactor vessel inl y

nozzle, a 135 in break at the reactor vessel outlet nozzle, and a 1000 in break at the steam generator inlet nozzle. The model and methods of analysis-

. used are described in Section 3.9.1.4.1 of the St. Lucie-2 FSAR. The analysis provided reactor vescel motions at the flange and snubber elevations for each in Response spectra plots for these locations are provideg hot ' leg of the cases.

Figures 3through6forthepgstulatedcoldlegbrcakandthe1000in break.

Results of the 135 in hot leg break are less conservative than the 1000 in2 break and are not included.

The asymmetric LOCA loads evaluation of the fuel assemblies was performed using.

detailed core models with single load path representations of the spacer grids.

The fuel assemblies were subjected to the resultan; displacements of the fuel alignment plate and core support plate which were obtained from the response analyses of the internals and fuel. The LOCA results of the fuel which include both one-sided and '.hrough-grid loads are presentcd in Figures 7 through 10 fc" the longest row across the core.

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4 COMPARIS0ft 0F SPACER GRID IMPACT LOADS WITH Pcrit VALUES NUREG-0609, " Asymmetric Blowdown Loads on PWR Primary Systems, Resolution of Generic Task Action Plan A-2, January 1981", states that it is a sufficient LOCA acceptance criterion to show that combined loads on the gr. ids remain below Pcrit.

It is our position that it is not necessary to combine seismic and LOCA loads on the grids.

For the convenience of the NRC review, the seismic and LOCA loads on the grids'have been combined (by SRSS*) and compared to values of Pcrit.

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