ML19320A767

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RCS Asymmetric Loads Evaluation Program, Final Rept,App a, Numerical Results, Evaluation of C-E Fuel.Nonproprietary Version.App B,Palisades Fuel Analysis,Encl
ML19320A767
Person / Time
Site: Millstone, Calvert Cliffs, Palisades, Fort Calhoun  Entergy icon.png
Issue date: 06/30/1980
From:
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, EMVC-EPS
To:
Shared Package
ML19320A739 List:
References
TASK-06-02.B, TASK-6-2.B, TASK-RR NUDOCS 8007020593
Download: ML19320A767 (26)
v • d • e


Text

i

!I g APPENDIX A ll NON-PROPRIETARY

!i 1,

REACTOR COOLANT SYSTEM

!i ASYMMETRIC LOADS I

EVALUATION PROGRAM

i j,

FINAL REPORT

i I

CALVERT CLIFFS 1&2 I

FORT CALHOUN

,I MILLSTONE 2 I

f in i!Iea serein I

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POWER l

SYSTEMS COMBUSTION ENGINEERING, INC.

i-

APPEllDIX A NON PROPRIETARY I

I REACTOR COOLANT SYSTEM ASYletETRIC LOADS

,E 3

FINAL REPORT NUMERICAL RESULTS - EVALUATI0il 0F CE FUEL I

Prepared by COMBUSTI0rl ENGINEERING, INC.

for CALVERT CLIFFS 1 & 2 FORT CALHOUN MILLSTONE 2 I

i-June 30, 1980

E l

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APPEf1 DIX A NUliERICAL RESULTS i

EVALUATIO!10F COMBUSTI0il EI!GIl!EERIllG FUEL i

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,.-~,m.-,-.,.-

w,%,.,y...e,%+,,,..,-__,,,%...,.9

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Appendix A g

1

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TABLE A-1

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l 14X14 SPACER GRID STRENGTilS AT ROOM TEllPERATURE I

ONE SIDED TliROUGli GRID l

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A.1

1 Appendix A L

TABLE A-2 l

FUEL ASSEMBLY COMPO!1ErlT STRESSES l

_GEllERIC PLAllT (CALVERT CLIFFS I AND 2, MILLSTONE 2)

Maximum Stress (ksi) l Component Base Case Revised Model Ratio

~

~

End Fitting Castings End Fitting Posts Guide Tubes Fuel Rods Allowable Stress (ksil _

Castings Posts Fuel Rods I

Guide Tube Properties Figure A-10 Yield Strength Strain Capability - Figure A-14 I

A. 2..-

n Appendix A L

TABLE A-3 i

SPACER GRID IMPACT LOADS GENERIC PLMIT (cal. VERT CLIFFS I AND 2,!!ILLSTONE 21 Maximum Impact Loads (lb)*

Peripheral Assemblies Interior Assemblies Case Max One-Sided Max Thru-Grid Max One-Sided Max Thru-Grid FPlB (1)

~

~

FPlB(2)

  • Listed as Revised Model (Base Case)

(1) Full Power Inlet Break - Core Direction Perpendicular to Hot Legs (2) Full Power Inlet Break - Core Direction Parallel to Hot Legs Spacer Grid Impact Strength (lb)

~

~

One Sided Thru-Grid Impact Load Ratios (Revised flodel/ Base Case)

Peripheral Assemblies

~

~

One Sided Thru-Grid Interior Assemblies

~

~

One Sided I

Thru-Grid I

A.3

Appendix A I

TABLE A-4 I

FUEL ASSEMBLY COMP 0flEllT STRESSES FT. Call!0Uti PLAflT_

Maximum Stress _(ksi)

Component Base Case Revised Model_

End Fitting Castings End Fitting Posts Guide Tubes Fuel Rods AllowableStress(ksil Castings Posts Fuel Rods Guide Tube Properties Yield Strength Figure A-10 Strain Capability -

Figure A-14 i

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Appendix A TAIILE A-5 SPACER GRID I!1 PACT LOADS FT. Call 100ft PLAf1T fjaximum Impact Loads (lb)*

Peripheral Assemblies Interior Assemblies Case Max One-Sided Max Thru-Grid flax One-Sided Max Thru-Grid

~

~

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(1) Full Power Inlet Brec.; - Core Direction Perpendicular to Hot Legs (2) Full Power Inlet Break - Core Direction Parallel to Hot Legs I

Spacer Grid Impact Strength (Lb.)

I One-Sided Thru-Grid A.5

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FIGURE A-1 l

FUEL ASSEMBLY LATERAL LOAD DEFLECTION CURVE 4

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FIGUllE A-2 FUEL ASSEMBLY LATEllAL IItPACT LOAD VS.

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Paga B-1 l

APPENDIX B l

PALISADES FUEL ANALYSIS lI A preliminary estimate has been obtained of the Palisades fuel assembly loads. These loads were obtained using plant specific Palisades fuel align-l ment plate, core support plate, aid core shroud motions obtained from the I

internals response analysis. These a tions vere employed with a standard CE 1h x 1h fuel assembly model. The results do not include the load reduction l

of about ten percent due to realistic treatment of the friction between the core barrel flange and reactor vessel support ledge.

l The preliminary results do not account for the differences between the CE 1h x 14 fuel assembly model and the Palisades fuel; which is supplied by Exxon. Most importantly:

l The Palisades fuel spacer grid stiffness is less than that of the CE I

~

1h x 14 fuel. It is expected that this difference vill decrease the magnitude of the spacer grid loads.

The spacing between Palisades fuel assemblies is greater than the spacing between fuel assemblies in the standard CE model. The effect of this difference has not yet been defined.

The crush properties of the Palisades fuel are different that those of the CE fuel.

It is expected that the allovable spacer grid load will be less than for CE fuel, i.e., about 2000 pounds for Palisades.

In addition, the reduced area properties of crushed Palisades grids have yet to be defined.

The specific steps which vill be taken to finalize results for Palisades fuel are as follows:

The standard CE lh x 1h fuel assembly model vill be revised to incorporate Palisades fuel assembly spacing. Spacer grid loads vill be obtained for

'this model, based on the Palisades fuel alignment plate, core plate and core shroud motions. The loads obtained from this analysis should be conservatively high, because they do not account for the reduced stiffness of the Palisades fuel.

Spacer grid impact tests vill be performed to determine the allovable grid impact loads. These tests vill also define the reduced area proper-ties of crushed grids, i.e., the overall grid reduction in area and the maximum localized reduction in area.

It is expected that these results vill demonstrate adequacy of the Palisades l

fuel spacer grids, i.e., show that:

ll

[. a Pag 2 B -l o

l APPENDIX B l

PALISADES FUL'L ANALYSIS I

A preliminary estimate has been obtained of the tulisades fuel assembly loads. These loads were obtained using plant specific Palisades fuel align-l ment plate, core support plate, and core shroud motions obtained from the I

hiternals response analysis. These metions were employed with a standard CE lh x 1h fuel assembly model. The results do not include the load reduction j

of about ten percent due to realistic treatment of the friction between the core barrel flange and reactor vessel support ledge.

The preliminary results do not account for the differences between the CE lh x'lb fuel assembly model and the Palisades fuel; which is supplied by Exxon. Most importantly:

l The Palisades fuel spacer grid stiffness is less than that of the CE B~

lh x lh fuel.

It is expected that this difference vill decrease the magnitude of the spacer grid loads.

f The spacing between Palit.ades fuel assemblies is greater than the B

spacing between fuel assemblies in the standard CE model. The effect of this difference has not yet been defined.

B The crush properties of the Palisades fuel are different that those of the CE fuel.

It is expected that the allovable spacer grid load vill l

be less than for CE fuel, i.e., about 2000 pounds for Palisades. In B

addition, the reduced area properties of crushed Palisades grids have yet to be defined.

l The specific steps which vill be taken to finalize results for Palisades fuel are as follows:

The standard CE lh x 1h fuel assembly model vill be revised to incorporate B

Palisades fuel assembly spacing. Spacer grid loads vill be obtained for this model, based on the Palisades fuel alignment plate, core plate and I

core shroud motions. The loads obtained from this analysis should be I

conservatively high, because they do not account for the reduced stiffness of the Palisades fuel.

l Spacer grid impact tests vill be perfomed to determine the allovable grid impact loads. These tests vill also define the reduced area proper-l ties of crushed grids, i.e., the overall grid reduction in area and the I

n'aximum localized reduction in area.

It is expected that these results vill demonstrate adequacy of the Palisades f

fuel spacer grids, i.e., show that:

l l

.

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