ML20087N254

Nonproprietary Shoulder Gap Data Taken on Batch D Assemblies After Cycle 3. Info Deleted

ML20087N254
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/30/1983
From:	ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML19268E739	List: 2CAN118310, Forwards Nonproprietary & Proprietary Shoulder Gap Data Taken on Batch D Assemblies After Cycle 3. Affidavit Encl. Proprietary Rept Withheld (Ref 10CFR2.790) ML20087N254
References
CEN-260(A)-NP, NUDOCS 8404030269
Download: ML20087N254 (6)

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s' ARKANSAS NUCLEAR ONE - UNIT 2 (-ANO-2)

SHOULDER GAP DATA TAKEN ON BATCH D ASSEMBLIES AFTER CYCLE 3 CEH-260(A)-NP e.

NOVEMBER , 1983 Combustion Engineering, Inc.

Nuclear Power Systems

.f* . Windsor, Connecticut

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8404030269 831202

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LEGAL NOTICE

• THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED l BY ColMUSTION ENGINEERING, INC. NEITHER COM8USTION ENGINEERING

- NOR ANY PERSON ACTING ON ITS BEHALF:

A. MAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPLIED INCLUDING THE WARRANTIES OF FITNESS FOR A PARTICULAR PURPOSE OR MERCHANTA8ILITY, WITH RESPECT TO THE ACCURACY, COMPLETENESS, OR USEFULNE3S OF THE INFORMATION CONTAINED IN THIS REPORT, OR THAT THE USE OF ANY INFORMATION, APPARATUS, METHOO, OR PROCESS DISCLOSED IN THIS REPORT MAY NOT INFRINGE PRIVATELY OWNED RIGHTS:OR R. ASSUMES ANY UA88LITIES WITH RESPECT TO THE USE OF, OR FOR DAMAGES RESULTING FROM THE USE OF, ANY INFORMATION, APPARATUS, METHOD OR PROCESS DISCLOSED IN THIS REPORT.

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. ARKANSAS NUCLEAR ONE - UNIT 2 (ANO-2)

SHOULDER GAP DATA TAKEN ON BATCH D ASSEMBLIES AFTER CYCLE 3

INTRODUCTION During the current E0C-3 refueling outage at ANO-2, measurements of remaining

,.- fuel rod shoulder gap were taken on the sixteen Batch D fuel assemblies listed in Table 1. For the C-E fuel assembly design, fuel rod shoulder gap is

'. defined 'as the distance between the bottom of the upper flow plate and the top of a fuel rod. The -information collected during this inspection program will be used to demonstrate that sufficient shoulder gap exists in Batch D Assemblies to accormnodate the additional closure that would result from a third operating. cycle in Reactor Cycle 4.

All shoulder gap measurements were trken using the C-E Comprehensive Fuel Inspection Stand (CFIS). The principal features of the CFIS that were used in this campaign included the fuel assembly elevator and turntable; and the

. periscope which is equipped with a micrometer filar attachment and a 35mm camera for color photography. The procedures used to obtain the raw data tabulated on the attached copies of the poolside inspection sheets will be described below. The method for calculating shoulder gaps' from the raw data will also be sumarized.

DISCUSSION One ~ inspection sheet is completed for each face of each fuel assembly examined.

For' identification during the inspection, the fuel assembly faces are designateC as North, South, East or West with the fuel assembly serial number being located in the Northeast corner of the upper end fitting. Fuel rods are

• numbered from left to right across an assembly face (1 to 16). Rows are 7* identified as 1 through 4 with the peripheral fuel rods (or row closest to g the periscope) being Row 1. Subsequent rows (2, 3, 4) are parallel to Row I and directly it.-

f The first operation performed on each fuel assembly after it was placed in the CFIS~ was to' verify its serial na:'er and serial number orientation. Then, at a suitable magnification, and with the gap of interest centered in the field

of. view, the micrometer filar on the periscope is aligned with the leading edge of the bottom of the upper flow plate (UFP) and the resulting micrometer e

W reading recorded on the daha sheet. Without moving the assembly, the filar is re-aligned with the top of the upper end cap of the fuel rod of interest and the corresponding reading recorded on the data sheet. ,

The difference in the micrometer readings between the UFP and fuel rod top

( 211m or 2hMR) should then be' multiplied 'by the appropriate micrometer constant (c) to arrive at the rod gap meassrement. _

These constants were determined by'using the periscope to measure a special Assembly Calibration Standard periodically during the inspection campaign. This Standard contains pre-characterized shoulder gaps of varying dimensions and at distances from the periscope corresponding to the first four rows of a 16x16 fuel assembly. Micrometer readings were obtained for each measurable shoulder gap in the standard using the same procedures employed for actual fuel assembly measurements (i.e. , leading edge of the bottom of the upper plate and the top of a simulated fuel rod).

The pre-characterized shoulder gap dimension is then divided by the difference in the corresponding micrometer readings to arrive at the micrometer constant for the particular row desired.

Finally, 35mm color slides were taken of the shoulder gap region of each face of each assembly involved in the measurement program as additional documentation to verify shoulder gap condition.

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TABLE 1 ANO-2 BATCH D FUEL ASSEMBLIE3 SELECTED FOR SHOULDER GAP MEASUREMENTS

, D002 D036 D006 D037

. D010 D039 0014 D040 ,

D027 D104 D028 D111 D031* D112 D034 D115 0

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