ML20134J978

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/Unit 2 Fuel Assembly Insp Program
ML20134J978
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/24/1996
From: Colburn D, Desiree Davis, Halligan J
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML17062B149 List:
References
PPE-96-135, NUDOCS 9611180165
Download: ML20134J978 (26)
v • d • e


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Westinghou23 Proprietary Clacs 3 1

Point Beach Unit 1/ Unit 2 Fuel Assembly inspection Program Contributors:

D. J. Colbum D. D. Davis J. R. Halligan A. S. Konzel H. Kunishi June 24,1996 1

inspection work was conducted at Point Beach by an NSD crew under the supervision of PPE contract engineer Jim Kisak. Responsibility for the reduction and verification of individual portions of the inspection program was assigred 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 Originating Engineer Verifying 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 J. Halligan D. Davis 4

4.0 F/A Length Meas;rements H. Kunishi A. Konzel 5.0 Rod to Nozzle Gap Measurements H. Kunishi A. Konzel 6.0 Overall Summary D. Colburn A. Konzel D. J. Colburn D. D. Davis

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Product Performance Engineering Product Performance Engineering H. Kunishi A. S. Konzel Product Performance Engineering Product Performance Engineering l

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9611180165 961016 PDR TOPRP ENVWEST B

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Product Performance Engineering l

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PPe-96140

westughoux proprutary cuso a 1.0 Background and Objectives 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 additional RCCAs did

.not. fully.. insert._A subseauent.inspectiortprograrrLIPfE-96:088Lconcluded.that_the. direct

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

(1) RCCA Drag Tests; (2) Guide Thimble Plug Gage Exams (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.

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 specific fuel features for each assembly are shown in Table 2.1. All of the assemblies share the following common features:

High Burnup Removable Top Nozzle Debris Filter Bottom Nozzle Solid Axial Blanket (natural UO )

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Integral Fuel Burnable Absorbers (IFBA) j The Vartage 5 fuel features with?</i the intermediate flow mixer (IFM) grid were used in j

fuel assemblies manufactured for contracts WEHO, WElO and WIFQ. Fuel assemblies l

manufactured for contract WEFQ did not have solid axial blankets (ABN) nor integral fuel l

burnable absorbers (IFBA).

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i Westinghous2 Proprietary Cls:s 3 Table 2.1: Fuel Features of Point Beach 14x14 Optimized Fuel Assemblies Seb,C i

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The drag test results are tabulated in Table 2.2 As shown in the table, some fuel assemblies were recently discharged from the reactor core and others '.iave been in the spent fuel pool for up to 2 cycles.

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Westinghous2 Proprietary Chss 3 3.0 Single Tube Probe i

Single tube probing was conducted on two fuel assemblies at Point Beach. The assemblies were selected based on their high burnup and high drag measurements as summarized i

below :

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Figure 3.1 DASHPOT PROBES "G0/NO G0" 14x14 FUEL ASSEMBUES i-l

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- Fuel Assembly Growth 4

Assembly length measurements were performed on a total of 10 ass.emblies (6 from Unit 1 and 4 from Unit 2). The measurements were made using a standarc! of known length and a measuring device with a dialindicator. The data was corrected for the spent fuel pool water temperature. Table 4.1 lists the measured growth for each of the 10 assemblies.

All 10 assemblies are of the 14x14 OFA design. Thimble tube material of assemblies V75, V76, V77, V78, Y11, and Z11 is Improved Zircaloy-4; that of V17,V20,V22, and V26 is standard Zircaloy-4.

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5.0 Fuel Rod Grov, The axial gaps between each peripheral rod and the assembly nozzles were measured from the low magnification TV tapes of 10 assemblies to determine fuel rod growth. The F/A Ids of tt. measured assemblies are V75, V76, V77, and V78 from Unit 2 and V17, V20, V22, V26, Y11, and Z11 from Unit 1.

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Summary of Point Beach Assembly Average Rod Growth

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6.0 Overall Summary Fuel assemblies tested at Point Beach displayed high drag forces in the lower part of the guide thimble major diameter in some assemblies. The contribution of the dashpot to the total drag (when the bottom of the RCCA is in the dashpot) was lower than that observed in the 17x17 fuel designs.

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Westinghousa Proprietary Class 3 1

Appendix 'A' Fuel Rod Growth Data Tables i

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