ML20134J986

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/Unit 2 Fuel Assembly Insp Program
ML20134J986
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/30/1996
From: Colburn D, Desiree Davis, Halligan J
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML17062B149 List:
References
PPE-96-180, NUDOCS 9611180171
Download: ML20134J986 (21)
v • d • e


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l WestinghounO Propdetary Class 3 l

1 Surry Unit 1/ Unit 2 Fuel Assembly inspection Program Contributors:

D. J. Colbum D. D. Davis J. R. Halligan

~ j A. S. Konzel '

H. Kunishi July 30,1996 Inspection work was conducted at Surry by an NSD crew under the supervision of PPE engineer Howard Pendley, 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 l

assignments is given below:

Insoection Program Sectl0D Originatina Enaineer Verifving Engineet 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. Colburn J. Halligan 4.0 F/A Length Measurements H. Kunishi A. Konzel 5.0 Rod to Nozzle Gap Measurements H. Kunishi A. Konzel 6.0 Overall Summary D. Colburn A. Konzel Signatures On File

D. J. Colburn D. D. Davis Product Performance Engineering Product Performance Engineering H. Kunishi A. S. Konzel l Product Performance Engineering Product Performance Engineering In 9611180171 961016 PDR TOPRP EMVWEST 8 PDR J. Halligan Product Performance Engineering ppe-96-249.c6 ppe-96-180

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Westhghous2 Proprietary Cla s 3 1.0 Background and Objectives RCCA insertion anomalies were recently experienced at Wolf Creek and South Texas.

During SCRAMS, several RCCAs failed to fully insert. Wolf Creek and South Texas

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conducted drop tests after their anomalies, and four additional RCCAs did not fully insert, gsubsequent _inspection , , , _ _,

program concluded that the direct cause of the incomplete RCCA

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

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

(3) Fuel Assembly (F/A) 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 six different contracts were drag tested in the spent fuel pool. The specific fuel features for each assembly are shown in Table 2.1. Most of the assemblies share the following common features:

  • High Burnup
  • Removable Top Nozzle Debris Filter Bottom Nozzle Table 2.1: Fuel Features of Surry 15x15 Optimized Fuel Assemblies a,b,e l

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Westksghouse Proprietary Class 3 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 have been in the spent fuel pool for up to 3 cycles. No distinction could be established for assemblies based on discharge time.

l Two assemblies from reoion.VPlF_l0F3 and 0F6Lstandard desian._were draa. tested as. cart *'."'*

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The burnup values in Table 2.2 were obtained from Virginia Power Company's June 13, 1996 response to NRC Bulletin 96-01 (Reference 2). Averaged RCCA drag values  ;

(withdrawal & insertion) were reported in that letter. Small differences exist between the '

values reported in that letter and the values reported in this memo. These differences appear to be a function of drag trace interpretation, and they have no impact on the conclusions reached.

Data from two different test agendas is shown in Figures 2.1, 2.2, and 2.3. Reactor trip testing was performed in response to NRC Bulletin 96-01. The spent fuel pool testing was performed to aid in determining the root cause behind the RCCA insertion problem. .,3,e

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Westinghouss Propdetary Clan 3 Table 2.2: Surry Drag Test Data

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l Westinhous2 hopnietary Class 3 Table 2.2 (continued): .Surry Drag Test Data i F- a,b,e

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ww w .% :.: yc w s Figure 2.1: Surry Dashpot and Upper Guide Thimble Drag Data (Reactor Trip and Spent Fuel Pool Testing) ,

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wanmos aa,.we ar ao a Figure 2.2: Surry Dashpot Drag and Fast Fluence Data (Reactor Trip and Spent Fule Pool Testing) l i

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wes w . w raycusaa Figure 2.3: Surry Upper Guide Thimble Drag and Fast Fluence Data j (Reactor Trip and Spent Fuel Pool Testing) a,b,e l

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3.0 Single Tube Probe i

Single tube probing was conducted on four fuel assemblies at Surry. The assemblies were  ;

selected based on burnup and drag measurements listed in Table 3.1 below. The probe '

information was used to establish the extent of susceptibility of 15x15 designs to the j insertion anomaly experienced previously at Wolf Creek.

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l Table 3.1: Assemblies Tested With Single Tube Probes a,b,e I

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l Table 3.2: Single Tube Probe Test Results

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Table 4.1: Surry Fuel Assembly Growth Data .,3,e l

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Westinghouse Proprietary Ciess 3 Figure 4.1: Recent Fuel Assembly Growth '

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lD Table 5.1: Summary of Surry Assembly Average Rof. Growth

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Wes&B Proprietary CJess 3 Figure 5.1: Assembly Average Rod Growth Data

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Appendix A Fuel Rod Growth Data l

for Surry Units 1 & 2 l

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