ML19347E691
| ML19347E691 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/04/1981 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML19260H447 | List: |
| References | |
| CEN-159(C)-NP, NUDOCS 8105130231 | |
| Download: ML19347E691 (14) | |
Text
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I POOR ORIGINAL i
!!ATERFORD DOCKET 50-382 CEft-159(C) t!P
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PRELIMl!!ARY ASSESS!:EllT OF IIATEf FORD-3 FL'EL STRUCTURAL I!1TEGRITY U!iDER FAULTED C0:;DITIO:!S MAY 4, 1981 COMBUST!0:1 E! Gl::EERI!!3, INC.
fiUCLEAR PO'.lER SYSTEMS P0h'ER SYSTE!'.5 CROUP WI!!DSCR, CONNECTICUT 06095 810513 O W
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t LEGAL NOT!CE Tills REPORT WAS PTIEPARED AS AN ACCOUfJT OF ViORK SPONSOTCO BY COf.*BUSTION ENGINEERif!G. If!C. NE11HER COf.iBUSTION ENGINEERING
!J R ANY PERSON ACTING OfJ ITS BEHALF:
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f.iAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IfdPLIFD INCLUDit!G THE WARRANTIES OF FITNESS FOR A PARTICULAR PURPCSE OR fiERCHANTABILITY, W!TH RESPECT TO THE ACCURACY, COf.1Pl.ETEf!ESS, OR USEFULNESS OF THE If FORT.iATION CONTAINED IN THIS
" REPORT, OR THAT THE USE OF ANY INFORT.iATIOfJ, APPARATUS, f.iETHOD, OR PF.OCESS DISCLOSEO IN THIS REPORT fdAY NOT INFRINGE PRIVATELY OWNED RIGHTS;OR B.
SSUf.iES ANY LIABILITIES WITH RESPECT TO THE USE OF,OR FOR DAf.iAGES RESULTING FRO *.1 THE USE OF, ANY fNFORT.iATION, AFPARATUS, IAETHOD OR PROCESS DISCLOSED If! THIS REPORT.
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. IfilROD_UCT 10:1 This docuacnt fnmily transmits the prelininary assessment of the !!aterford-3 fuel structural integrity under faulted conditions.
Trie contents of this document were presented at a joint C-E/t4RC/EGSG meeting on April 28, 1981.
The seismic analysis methods and nodels presented utilize the methodology of the C-E fuel topial report, CEtlPD-178 (Ref.1).
The LCCA analysis methods and models represent an initial improvement over the LOCA methodology in CEriPD-178, and are essentially based on the fuel seismic models from the topical report.
These results represent the best information for 'laterford available at this time.
The final assessment of the 1laterford-3 fuel structural integrity under seisnic and LOCA loadings will be pro /ided in February 1932.
The final assess"ent will utilize the recently developed rathods and r:adels utilized and presented (Ref. 2) on the San Onofre cM e'.
A description of these current methods and models was also presented at th: '.pril 28, 1981 meeting.
...w Ref.1 "CEt!PD-178, Structural Analysis of fuel A*.semblies for Combined Seismic and Loss of Coolant /.ccident Loading", C-E Proprietary Report, August 1976.
Ref. 2 "CEti-151(S)-P, Data Transmittal for Review of SCE fuel Strucutral Integrity Under faulted Conditions", C-E Proprietary Report, fiarch 1981 POOR ORIGINA
2-Pf:ELIMIfMRY SEiS!11C A!1ALYSIS OF FUEL The preliminary seismic analysis of the Uote. ford fuel assemblics tras performed by the procedure outlined in CEf'PD-178 (Ret. i).
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 horizontel, vertical and rotational (rocking) tit.e history responses of the reactor vessel determined from the reactor coolant system seismic analysis.
flext, this excitation was input into separate horizontal cnd vertical r:odels of the reactor internals plus core.
For the horizontal direc-tion, 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 shroud viere input into a detailed core model representing the longest ro'. acr'oss the core (17 fuel assemblics).
For the vertical direction, the core response was obtained directly from the coupled internals plus core analyses.
The results of the Uaterford-3 core preliminary seismic analysis are sho' n on Figures 1 and 2.
They consist of peak one-sided and through-grid spacer grid ir. pact leads for the Safe Shutdorn Earthquake (SSE).
These results are for the longest ro across the core.
e P00R OR!GlNM
g PRELIM!ilARY LOCA'AtlALYSIS OF FUEL _
e The preliminary asymmetric LOCA loads evaluation of the Waterford-3 fuel assemblies was performed utilizing the detailed core model (previously developed for the
' Waterford-3 seismic analysis) subjected to core plate motions and core shroud The motions obtained fron-the asymmetric LOCA loads evaluation of San Onofre - 2.
corresponding motions for the Waterford-3 internals are not yet evailable.
A structural analysis of the Waterford-3 reactor coolant system for a postulated The model and pipe break at the reactor vessel inlet nozzle has been perfonted.
The methods of analysis are describcd in Appendix 5.4A cf the Waterford-3 FSAR.
resultant reactor vessel r..ctions at the core support barrel flange and snubber elevations were determined and corresponding response spectra were calculated.
The spectra are shown in Figures 3 and 4.
2 The Waterford-3 postulated pipe break area (350 in ) and opening time (6 milli-seconds) are identical to those for San Onofre - 2.
The reactor coolant system geometry for Waterford-3 is also identical to that for San Onofre - 2.
The.
reactor vessel support sy:te ef Waterford-3 is similar to that of San Onofre - 2 in that both vessels are succorted by a pad under each inlet nozzle.
The response spectra corresponding to the San Onofre - E reactor vessel motions of the core support barrel flange and snubber elevations are shown in Figures 5 and 6, fcr comparison with thuse of Waterford-3.
The reactor vessel internals for the tv.o plants are essential?y identical.
. The results of the Waterford-3 preliminary asymmetric LOCA evaluation of the fuel are presented in Figures 7 and 8.
They consist of peak one-sided and through-grid These results are spacer grid impact loads resulting from the postulated LOCA.
for the longest row across the core (17 fuel assemblies).
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COMPAPIS0N OF_ SPACER GRID IMPACT LOADS UITH Perit VAf UES
!!OREG-0609, " Asymmetric Blowdown Loads on PWP, Prirmry 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 grids 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 flRC review, the seismic and LOCA loads on the grids have been combir.ed (by SRSS*) and compared to values of Pcrit.
Peak Peak Peak Pcrit LOCA SSE Combined Load Load Lead
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- The combinea lo As are obtained from the scuare root of the som of the squa.es of the SSE and LOCA loads for the same grid (function of grid location).
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