ML20134J989

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Fuel Assembly Insp Program Phase 2
ML20134J989
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 09/06/1996
From: Colburn D, Desiree Davis, Halligan J
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML17062B149 List:
References
PPE-96-217, NUDOCS 9611180175
Download: ML20134J989 (29)
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Wutinghouse Proprietary Class 3 1

Wolf Creek Fuel Assembly inspection Program Phase 2 I

l Contributors:

D. J. Colburn i

D. D. Davis J. R. Halligan A. S. Konzel H. Kunishi September 6,1996 Responsibility for the reduction and verification of individual portions of the inspection program was assigned to various PPE engineers. Their signatures on this document attest that (1) they i

have independently verified the sections assigned to them; and (2) they concur with the results documented herein.

1 Insoection Program Section Oriainatina Enaineer Verifvina Enaineer 1.0 Background & Objectives D. Colburn J. Halligan 2.0 Full Length RCCA Drag Tests J. Halligan D. Davis 3.0 Guide Thimble Plug Gage Exams J. Halligan D. Davis 4.0 Fuel Assembly Growth Data H. Konishi A. Konzel 5.0 Fuel Rod Growth Data H. Kunishi A. Konzel 6.0 Fuel Assembly Bow Data D. Davis D. Colburn 7.0 Visual Inspections D. Davis D. Colburn 8.0 Overall Summary J. Halligan D. Davis Signatures On File D. J. Colburn D. D. Davis Product Performance Engineering Product Performance Engineering H. Kunishi A. S. Konzel

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Product Performance Engineering Product Performance Engineering J. R. Halligan j

Product Performance Engineering 9611100175 961016 PDR TOPRP EMVWEST B

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Westinghouse Proprietary Class 3 1.0 Background and Objectives An RCCA insertion anomaly was experienced at Wolf Creek and South Texas Unit 1.

During SCRAMS, several RCCAs did not fully insert. Wolf Creek conducted cold drop tests after the event and additional RCCAs did not fully insert. A subsequent inspection program

_ concluded.that_tha. direct cause of_the_incomolete RCCA insertions atWolf_ Creek was _a b.c r

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The objective of the Phase 2 Wolf Creek inspection program was to build on the results of the originalinspection program (PPE-96-088). The following tests were scheduled to be conducted during the inspection program:

4 (1) RCCA Drag Tests; (2) Guide Thimble Plug Gage Exams (Single Tube Probe Tests);

(3) Fuel Assembly Length Measurements; (4) Fuel Assembly Bow Measurements; (5) Fuel Rod-to-Nozzle Gap Measurements; (6) Detailed Visual Inspections; (7) Fuel Rod Oxide Measurements; j

(8) Fuel Rod Profilometry Measurements; (9) Top Nozzle Spring Load / Deflection Measurements; (10) Lateral Grid Width Measurements; (11) Grid Cell Size and Force Measurements; and (12) Disassembly of H50 and H38 fuel assembly elements for hot cell examinations.

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Fuel assembly length measurements and fuel rod-to-nozzle gap measurements were needed to determine if the growth of these fuel assemblies and fuel rods is within the anticipated i

range. The fuel rod oxide and profilometry results (items 7 and 8) were presented in PPE-96-204. The results of the top nozzle spring load / deflection measurements, lateral grid width measurements, grid cell size and force measurements and hot cell investigations will be presented in later reports.

1 2.0 Full Length RCCA Drag Tests in the Spent Fuel Pool

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g The results of the additional fuel assembly testing and skeleton assembly drag testing are provided below. Additional 'G' region and 'H' region assemblies were examined to gather additional information and to record differences between the regions.

1 ppe-96-249,c7 ppe-96 217

Westinghous) hoprietary Class 3 Fuel Assemblies i

Six additional fuel assemblies were selected for drag testing. Two 'G' region and four 'H' region assemblies were tested. The 'G' region assembly burnup values were 35 and 54 GWD/MTU The 'H' region assembly burnup values were 37.2,40,44 and 49 GWD/MTU.

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After the fuel rods were removed from fuel assembly H50, a drag check measurement was performed with the dummy RCCA. The purpose was to determine what difference, if any, could be measured with the fuel rods removed. The measurements were taken in the new fuel elevator with the skeleton clamped down.

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Figure 2.1: Dashpot and Upper Guide Thimble Drag Data

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Westinghousa Proprietary Class 3 3.0 Guide Thimble Plug Gage Exams The single tube probing was performed on the dashpot of fuel assembly G68. This

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I 4.0 Fuel Assembly Growth Data The fuel assembly length measurements were performed on an additional 8 assemblies (2 assemblies from Region G,2 assemblies from Region J and 4 assemblies from Region H). _*'"'"

The 'G' assemblies have the 17x17 Standard design while the 'J' and 'H' assemblies have the 17x17 V-5H design. The 'G' assemblies use standard Zircatoy-4 as the thimble tube material, but improved Zircaloy-4 is used for the 'J' and 'H' assemblies.

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Westhghouss Propdetary Class 3 Figure 3.1: DASHPOT PROBES "G0/NO G0" 17x17 FUEL ASSEMBUES a,b,c "j

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5.0 Fuel Rod Growth Data The axial gaps between each peripheral rod and the assembly nozzles were measured from the low magnification TV tapes of 10 Wolf Creek assemblies to determine fuel rod growth.

The assemblies were G33, G68, H35, H53, H54, H61, H67, H83, J32, AND J37.

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t 6.0 Fuel Assembly Bow Data In the first phase, the corrected assembly bow shape and bow magnitude was provided for

_seventeertt12LfueLassemblies._Thelow_for_ assemblies.H502nd.H3ELwas_re-measured 1v_* b c I

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Figure 7.1: Grid 7 relocated to Grid 8 during Phase 1 Testing l

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Figure 7.2: Examples of Thimble Tube Disiartion for Assembly H50

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r Appendix A Fuel Assembly Growth Data For Wolf Creek - EOC-8 l

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Figure C.2: Fuel Assembly H38, Face 2 Bow Data - Profile

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Figure C.3: Fuel Assembly H50, Face 4 Bow Data Direct View i

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