ML20134J974

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V C Summer Fuel Assembly Insp Program
ML20134J974
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/05/1996
From: Colburn D, Desiree Davis, Konzel A
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML17062B149 List:
References
PROC-960605, NUDOCS 9611180163
Download: ML20134J974 (9)
v • d • e


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Westinghouse Proprietary Class 3 l

V. C. Summer Fuel Assembly inspection Program Contributors:

D. J. Colbum D. D. Davis A. S. Konzel H. Kunishi June 5,1996

, inspection work was conducted at V. C. Summer by an NSD crew under the supervision of PPE

engineer Tom DiMuzio. 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 have independently verified the sections assigned to them; and (2) they concur with the results documented herein. A listing of the individual data reduction and verification assignments is given below

Insoection Program Section Oriainating Engineer Verifving Engineer 1.0 Background & Objectives A. Konzel D. Colburn 2.0 Full Length RCCA Drag Tests D. Davis D. Colburn 3.0 Guide Thimble Plug Gage Exams D. Davis D. Colburn 4.0 F/A Length Measurements H. Kunishi A. Konzel 5.0 Overall Summary D. Colburn A. Konzel l Signatures On File D. J. Colburn D. D. Davis Product Performance Engineering Product Performance Engineering ,

H. Kunishi A. S. Konzel Product Performance Engineering Product Performance Engineering 9611180163 961016 PDR TOPRP EMWEST B PDR ppe-96 249,c3 ppe-96-135 i

Westinghouso Proprietary CInse 3 1.0 Background and Objectives l

An RCCA insertion anomaly was experienced at Wolf Creek near the end of Cycle 8.  !

The' reactor tripped resulting in a SCRAM. During this SCRAM, five RCCAs failed to fully insert. Wolf Creek conducted cold drop tests after the anomaly, and three i additional RCCAs did not _fu._ll.y insert. A subsequ_ent inspec_tio_n pr_ogram (PPE

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The following tests were scheduled to be conducted during the inspection program:

(1) RCCA Drag Tests; (2) Guide Thimble Plug Gage Exams (also referred to as Single Tube Probe Tests);

(3) Fuel Assembly Length Measurements; and (4) Fuel Rod-to-Nozzle Gap Measurements.

Fuel assembly length measurements and fuel rod-to-nozzle gap measurements were needed to establish that the growth of the fuel assemblies and fuel rods is within the anticipated range for the listed F/A burnup.

Guide thimble plug gage exams (Item #2 above) and videotaping of the rod-to-nozzle gaps (ltem #4 above) for each of the V. C. Summer fuel assemblies was not completed due to time limitations. Plug gage and fuel rod growth data are therefore unavailable for V. C. Summer at this time.

2.0 Full Length RCCA Drag Tests in Spent Fuel Pool Fuel assemblies fabricated for four different contracts were drag tested in the spent fuel pool. The special features of the fuel assemblies are shown below in Table 2.1.

As shown in the table the common feature in the assemblies are as follows:

Integral Fuel Burnable Absorbers (IFBA)

Intermediate Flow Mixing Grids (IFMs)

Removable Top Nozzle Debris Filter Bottom Nozzle ppe-96 249,c3 ppe-96 135

l Westhwhous2 Proprietary Class 3 l

The CGGF and CGHF assemblies have many of the features included in the Vantage +

l design. The CGFF assemblies have many of the features included in the Vantage 5H design while the CGIF assemblies have many of the features in the Performance +

design.

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! Table 2.1: Fuel Features of VC Summer 17x17 Optimized Fuel Assemblies .,b,e

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ABN ~

solid Axial Blankets (natural) HIBU + Modified Assembly for Higher Burnup HIBU Modified Assembly for High Burnup VPs Variable Pitch Plenum spring

, IFBA Integral Fuel Burnable Absorber ZRLC ZlRLO Fuel Rod Cladding

! IFM Intermediate Flow Mixing Grid ZRLT ZlRLO Guide Thimbles / Instrument Tube i RTN Removable Top Nozzle AABE Annular Axial Blankets (enriched)

DFBN Debris Filter Bottom Nozzle CC oxide-Coated Cladding AABN Annular Axial Blankets (natural) ZRLMG ZlRLO Mid-Grid / IFM The drag test results are tabulated in Table 2.2 and are graphed in Figures 2.1, 2.2 and 2.3. As shown in Table 2.2 most fuel assemblies were recently discharged from the reactor core and others have been in the spent fuel pool for 1 cycle. e,b,e

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Westkwhouse Proprietary CInss 3 Figure 2.1: VC Summer Dashpot and Guide Thimble Data

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westherwao hopnr etery coess 2 Figure 2.2: VC Summer Dashpot Drag and Fast Fluence Data 6

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Westingknose Proprietary CAnsa 3 Figure 2.3: VC Summer Guide Thimble Drag and Fast Fluence Data r a,b.c

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wuthwhoua nopektuy chu 2 l' 3.0 Single Tube Probe l

L Singplube probe testing was not conducted at V.C. Summer due to time limitations during the refueling outage.

1 4.0 Fuel Assembly Growth Fuel assembly length measurements were performed on a total of 8 assemblies (4 F/As

! from Region H and 4 F/As from Region J). The measurements were made using a standard of known length and a measuring device with a dial indicator. The data was corrected for the spent fuel pool water temperature. Assembly J34 that was stored in the SFP was re- l measured to verify the accuracy of the assembly length measuring tool. Table 4.1 lists the  !

measured assembly length and growth values for each of the 8 assemblies.

"H" assemblies are of the 17x17 Vantage-5 design and "J" assemblies are of 17x17 Vantage + design. The thimble tube material in assemblies H46 & H51 is Improved l l Zircaloy-4; assemblies H47 & H50 have standard Zircaloy-4 thimbles; assemblies JO9, J10, J13, and J22 have ZlRLO@ thimbles .  !

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Table 4.1: V. C. Summer Fuel Assembly Growth Data **b'*

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I Figure 4.1: Fuel Assembly Growth Plot SAP, VRA, CGE, WEP, GAE l a,b,e 1

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5.0 Overall Summary j

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