ML20070V425

Forwards Info Re GE Response to Gessar II Question 490.01, Re Fuel Rod Cladding & Deformation Per M Tokar Request at 830125 & 26 Meetings

ML20070V425
Person / Time
Site:	05000447
Issue date:	02/09/1983
From:	Charnley J GENERAL ELECTRIC CO.
To:	Berlinger C Office of Nuclear Reactor Regulation
References
CON-JSC-11-83 JSC-011-83, JSC-11-83, MFN-028-83, MFN-28-83, NUDOCS 8302170335
Download: ML20070V425 (4)

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GENER AL h ELECTRIC NUCLEAR POWER SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 682, (408) 925-3697 MFN-028-83 JSC-011-83 February 9, 1983 yu- W U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 Attention: Mr. C. H. Berlinger, Chief Core Performance Branch Gentlemen:

SUBJECT:

GESSAR II REVIFW - NRC REQUEST FOR INFORMATION The attached information is provided at the request of Mike Tokar. This information was discussed with him in our meetings of January 25 and 26,1983, regarding our response to Question 490.01 on GESSAR II.

Very truly yours, d

. S. Charnley /

Fuel Licensing Manager Nuclear Safety and Licensing Operation JSC:hmm/002087 Attachment 500 3 g):/7(ade?Y6

0302170335 830209 PDR ADOCK 05000 A

I A.

ITEM BASIS Cladding Stress The fuel rod cladding is evaluated i

to ensure that the fuel will not fail due to fuel cladding stresses exceeding the cladding mechanical capability.

Fatigue The fuel rod cladding is evaluated to ensure that the fuel will not fail due to cyclic fuel rod loadings exceeding the cladding fatigue capability.

Fretting Wear The fuel assembly is evaluated to ensure that the fuel will not fail due to fretting wear of the assembly components.

Crud, 0xide The fuel rod is evaluated to ensure that the cladding temperature increase and cladding metal thinning due to cladding corrosion, and the cladding temperature increase due to the buildup of corrosion products, do not result in fuel rod failure due to reduced cladding strength.

Rod Bowing The fuel rod is evaluated to ensure that fuel rod bowing does not result in fuel failure due to boiling transition.

Irradiation Growth The fuel assembly is evaluated to ensure that irradiation-induced axial growth does not result in fuel failure due to insufficient axial expansion space.

Rod Pressure The fuel rod is evaluated to ensure that the effects of fuel rod internal pressure will not result in fuel failure l

due to excessive cladding pressure loading.

Hydraulic Loads The fuel assembly is evaluated to ensure that interference sufficient to prevent control blade insertion will not occur.

Control Rod Reactivity The fuel system is evaluated to ensure that the reactivity control required to bring the reactor to cold shutdown is maintained.

B.

ITEM BASIS Hydriding The fuel rod is evaluated to ensure that failure will not occur due to internal cladding hydriding.

Cladding Collapse The fuel rod is evaluated to ensure that fuel rod failure due to cladding collapse into a fuel column axial gap will not occur.

Fretting -----

Cladding Overheating The fuel rod is evaluated to ensure that fuel rod failure due to boiling transition cladding overheating will not occur.

Fuel Pellet Overheating The fuel rod is evaluated to ensure that fuel rod failure due to excessive fuel melting will not occur during steady-state operation.

Fuel Enthalpy Fuel rod failure during severe reactivity initiated accidents is evaluated to ensure no underestimation of the number of fuel rod failures. >

Pellet-Clad Interaction The fuel rods are evaluated to en:ure fuel rod failure due to pellet-clad mechanical interaction excluding internal environmental effects will not occur during anticipated operational transients.

Bursting The fuel assembly is evtluated in compliance with the requirements of 10 CFR 50 Appendix K as it relates to the incidence of rupture during a LOCA.

Mechanical Fracturing The fuel rod is evaluated to ensure that mechanical fracturing will not occur as a result of hydraulic loads or a load derived from core-plate motion.

L t

C.

ITEM BASIS Clad Embrittlement The fuel assembly is evaluated in compliance with 10 CFR 50.46 as it relates to cladding embrittlement during a LOCA.

Violent Expulsion of Fuel Severe reactivity initiated accidents are evaluated to ensure that widespread fragmentation and dispersal of the fuel will not occur.

Clad Melting See Clad Embrittlement.

Fuel Rod Ballooning The fuel assembly is evaluated in compliance with 10 CFR 50 Appendix K as it relates to the degree of fuel cladding swelling and rupture during a LOCA.

Structural Deformation The fuel assembly is evaluated under SSE and LOCA loading conditions to ensure that loss of fuel assembly coolability,and interference to the degree that control blade insertion is prevented, will not occur.

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