RS-12-082, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)

Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)

ML12136A021
Person / Time
Site:	Clinton
Issue date:	05/14/2012
From:	Gullott D Exelon Nuclear, Exelon Nuclear Security
To:	Office of Nuclear Reactor Regulation, Document Control Desk
Shared Package
ML121360021	List: RS-12-082, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)
References
RS-12-082, eDRF Section 0000-0145-1983, eDRF Section 0000-0145-5557, TAC ME1643 0000-0145-1983-NP, 0000-0145-5557-NP
Download: ML12136A021 (66)

Text

Exelon Nuclear Security, LLC wwwexeloncorp.com 4300 Winfield Road Nuclear Warrenville, IL 60555 Attachments 1 and 3 contain proprietary information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachments 1 and 3, this cover letter is decontrolled.

RS-12-082 May 14, 2012 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Reports Associated with Results of Post-Irradiation Examination (PIE) of Global Nuclear Fuel (GNF) GE14i Isotope Test Assembly (ITA)

Reference:

Letter from C. S. Goodwin (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC), "Clinton Power Station, Unit No.1 -Issuance of Amendment Re: Request to Modify Facility Operating License in Support of the Use of Isotope Test Assemblies (TAC NO. ME1643)," dated January 15, 2010 The purpose of this letter is to report the results of portions of the PIE of a GNF GE14i ITA bundle performed by GNF for Facility Operating License No. NPF-62 for Clinton Power Station.

The reporting of this information was required by the NRC as discussed in Condition 11 of the Conditions and Limitations section of the referenced letter.

The attached information fulfills the poolside visual and combined instrumentation measurement system (COINS) examination requirements discussed in Condition 11 of the referenced letter.

The results of the poolside gamma scanning and destructive examinations will be reported when the results of those examinations become available.

Attachments 1 and 3 contain proprietary information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachments 1 and 3, this cover letter is decontrolled.

May 14, 2012 U. S. Nuclear Regulatory Commission Page 2 This submittal is subdivided as follows.

• Attachment 1 provides a proprietary version, including an affidavit from GNF attesting to the proprietary nature of the information, of the results of pools ide visual examinations of a GE14i ITA.

• Attachment 2 provides a non-proprietary version of the results of the poolside visual examinations of a GE14i ITA.

• Attachment 3 provides a proprietary version, including an affidavit from GNF attesting to the proprietary nature of the information, of the results of COINS examinations of a GE14i ITA.

• Attachment 4 provides a non-proprietary version of the results of COINS examinations of a GE14i ITA.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.

David M. Gullott Manager - Licensing Attachments:

1. Clinton Power Station EOC13 Fuel Examination & GE14i (ITA) Rod Retrieval, December 2011 - Proprietary

2. Clinton Power Station EOC13 Fuel Examination & GE14i (ITA) Rod Retrieval, December 2011 - Non-Proprietary

3. Clinton Power Station EOC13 COmbined INStrumentation Measurement System (COINS)

Data Report, Measured December 2011 - Proprietary

4. Clinton Power Station EOC13 COmbined INStrumentation Measurement System (COINS)

Data Report, Measured December 2011 - Non-Proprietary

AITACHMENT 2 Clinton Power Station EOC13 Fuel Examination & GE14i (ITA) Rod Retrieval, December 2011 -

Non-Proprietary

Global Nuclear Fuel A Joint Venture of GE, Toshiba, &Hitachi 0000-0145-5557-NP eDRF Section 0000-0145-5557 March 2012 Non-Proprietary Information - Class I (Public)

Fuel Examination Services Field Test Report Clinton Power Station EOC13 Fuel Examination & GE14i (ITA) Rod Retrieval December 2011 Copyright 2012 Global Nuclear Fue/- Americas, LLC All Rights Reserved

0000-0145-5557-NP Non-Proprietary Information - Class I (Public)

FUEL EXAMINATION SERVICES FIELD TEST REPORT

(

Reference:

PRI 21-01)

.§~_e .. _ ._ _ __

TITLE: Clinton EOC13 GE14i (ITA) Fuel Examination & Rod Retrieval DATE: December 2011, Rev. 0 ii

0000-0145-5557-NP Non-Proprietary Information - Class I (Public)

INFORMATION NOTICE This is a non-proprietary version of the document 0000-0145-5557-P, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )).

IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The only undertakings of Global Nuclear Fuel-Americas, LLC (GNF-A) with respect to information in this document are contained in contracts between GNF-A and its customers, and nothing contained in this document shall be construed as changing those contracts. The use of this information by anyone other than those participating entities and for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF-A makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.

This document records technical information status at the date of publication and may not represent final disposition or conclusion related to the reported study. Changes in test data, analytical models, and evaluations subsequent to publication of this document may supersede the reported work and verification of applicability should be made before results are used in final design work.

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1.0 INTRODUCTION

In accordance with an agreement between Exelon and GNF, an irradiated fuel examination of one GE14i Isotope Test Assembly (ITA) was performed during the Clinton Power Station EOC13 refueling outage in December 2011 by GNF.

Clinton is a GE BWRl6 at which GNF has performed channel exams and replacements during the last few outages. This was the first irradiated fuel inspection with bundle disassembly activities conducted at Clinton. The visual exam and measurement data will be used to evaluate the performance of one of the eight GE14i ITAs installed in Clinton for Cycle 13. COINS (fuel rod 00 liftoff and profilometry) and gamma scan (fuel rod power, segmented isotope rod activation) data was taken on a mix of standard GE14 fuel rods and segmented isotope rods. Additionally, one segmented isotope rod was removed, disassembled into its segments and placed into a cask shipping rack for retrieval and shipment to GEH's Vallecitos Nuclear Center after the outage.

This segmented isotope rod was replaced with a new segmented isotope rod. Gamma scanning requires that fuel rods could not begin until ten days after plant shutdown but all other project activities were completed as soon as the fuel became available.

The Water Submersible Gamma Spectrometer system (WSGS) performs gamma spectroscopy measurements on irradiated fuel rods or segmented isotope rods in a utility spent fuel pool or other adequate underwater pool. The data collected is gamma spectra, which is acquired at specified axial positions of the rod. Subsequent data processing will generate isotope specific information as a function of location. The system consists of a watertight, submersible, shielded detector housing with integrated collimator, variable aperture device, variable absorber device, and rod positioning fixture. A High Purity Germanium (HPGe) detector is coupled to a liquid nitrogen dewar that employs an automated liquid nitrogen fill system and is installed into the housing. An integrated rod positioning, motion control and data acquisition system assists in the acquisition of spectral data. Rigging and mounting hardware support the system while a rod grapple secures and controls the rod as it is positioned in front of the WSGS.

2.0 WORK SCOPE &

SUMMARY

The work scope performed is identified in Table 1. Visual characteristics observed for the bundle and individual rods are listed in Table 2.

The examination work scope included a bundle visual inspection on all four sides for the assembly in the unbrushed condition. The bundle side identification convention reflects the GNF designations of sides 3 and 4 adjacent to the control blade (CB) with 1 and 2 away from the CB.

Sides 1 through 4 advance in a clockwise direction looking down from the top of the bundle.

0000-0 145-5557-NP Non-Proprietary Information - Class I (Public)

The following sections will provide detailed visual findings that are noteworthy relative to what is normal (from Table 2). In all cases, the findings are not significantly atypical for irradiated fuel.

That is, some types of debris (crud flakes or clumps or fiber-like) are not harmful, some spacer movement is acceptable (minor raising or cocking) and some variance in rod-to-rod spacing is acceptable (provided rods are not close to touching). No rod gap variation of 50% or more closure was observed.

3.0 GE14i Isotope Test Assembly (ITA) - JYK690 The assembly was installed in the Fuel Prep Machine (FPM) and the channel fastener and channel were removed. A bundle peripheral visual exam was completed. Moderate to heavy crud was seen on the fuel rods however the crud was much lighter on the segmented isotope rods. The Upper Tie Plate (UTP) was removed. All segmented isotope rods were lifted slightly to confirm that no segments had unscrewed; all segments were tight. (( )) standard GE14 fuel rods ((( ))) had visual exams (and COINS measurements -

separate report) completed. All segmented isotope rods ((( ))) had visual exams and COINS measurements (COINS - separate report). During visual of the segmented isotope rods, the A1-B1 cell locations of all spacers were visually examined from both above and below the spacers with nothing atypical observed. The visual exam confirmed that the fuel bundle/rods and segmented isotope rods are performing as designed with no atypical results.

The customer was informed that this bundle was acceptable for reinsertion during the outage (pending no issues during later gamma scanning of fuel rods or bundle reassembly - none occurred). The segmented isotope rods were gamma scanned to measure relative activity levels at 3 axial locations for each of the segments (separate report).

The (( )) segmented isotope rod was removed from the bundle and disassembled. The disassembly of the segmented rod proceeded without any issues. Each of the segments was loaded into pre-designated locations in the cask basket. After all segments were loaded, the cask basket was moved to the cask pit and lowered to the pool floor. A new segmented isotope rod (s/n 1158CBT) was inspected and installed in to the (( )) rod location.

Gamma scanning of (( )) fuel rods began at the completion of the above work. (( ))

full length rods (((

))) and (( )) partial length rods ((( lJ) plus the (( )) reference rod had gamma scans completed (again, those results will be provided in a separate report).

All rods that were gamma scanned were moved from the FPM to the cask pit area (gamma scanner location) by the refueling bridge using two 6-hole/rod storage containers ((

)) with the ref. rod remaining at the gamma scanner for periodic rescans). All rods were returned to the bundle. The 2

0000-0145-5557-NP Non-Proprietary Information - Class I (Public) bundle was reassembled with new lock tabs and nuts. The channel and channel fastener were installed and proper torque applied. The assembly was confirmed acceptable for continued irradiation/operational use. The assembly was returned to the spent fuel racks and was returned to the core for continued operation.

Photographs summarizing the visual inspection are attached including (elevation info. in all photos is in inches from the Lower Tie Plate top surface):

• Figure 1: JYK690 Bundle Observations

• Figure 2: JYK690 Individual Rod (fuel rod) Observations

• Figure 3: JYK690 Individual Rod (segmented isotope rod) Observations Noteworthy observations for JYK690:

• Moderate to heavy crud on bundle

• Spacers 1-3 heavy crud

• Segmented isotope rods have lighter crud than rest of rods

• Segmented rod sections- none unscrewed NOTE: On Dec. 6, (GEH/GNF fuel inspection team's fatigue day off), the Fuel Handling Building Spent Fuel Pool was placed into a fuel pool cooling system alignment resulting in heavy turbulence.

The inspection team's stainless steel bucket which was hanging from the curb 3_4' to the left of the fuel prep machine held four locktab washers and eight hex nuts from the bundle disassembly at the time of the SFP water turbulence. The turbulence resulted in all these parts being washed out of the bucket. Only three of the four locktab washers & five of the eight hex nuts were located and retrieved back into the bucket. The other four pieces (one locktab washer and three hex nuts) are missing and believed to be at rest at the bottom of the SFP. The bundle was visually examined after this incident and no foreign material (other than small floating fibrous-like material) was seen in the bundle.

5.0 CONCLUSION

The GE14i ITA assembly JYK690 is suitable for continued operation. Overall fuel performance is excellent.

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TABLE 1 - Examination Plan GWd/MTU Fuel Bundle Reload at EOC13 Desian InsDeetion Work seoDe Comments JYK690 12 -20 GE14i Bundle Visual Inc!. spacer cell visuals w/segmented isotope rod(s) removed Fuel Rod Visual/COINS (( )) Co-60 rods (((

))) & (( )) fuel rods visual/COINS (((

)))

Gamma scan rods (( )) Co-60 rods (((

(Co-60 activity or fuel rod power);

Fuel rods: begin at (( )) above ))), ref. rod ((( )))

BAF & stop (( )) below TAF; &(( )) fuel rods every (( ]) for (( )); gamma scan (((

every (( )) for next (( n rods; every (( )) for (( )) rods; Ref. rod ((( ))) scanned ((

)) times first at every (( )), then every (( )) rods)

Co-60 rods: every (( )) for )))

Co-60 rods (3 scans per segment)

• =PLR 4

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Table 2 - Visual Characteristics Observed Bundle Periphery*

• Upper and lower tie plate/component condition

• Expansion spring compression

• Upper and lower end plug weld and heat affected zone appearance

• Peripheral fuel rod and spacer band oxide coverage (if not covered by crud)

• Bar code region corrosion condition where present

• Spacer band weld integrity

• Spacer location

• Presence of obvious foreign material (debris)

• Crud deposition characteristics

• Visible rod-to-rod spacing on all assemblies

• Partial length rod (PLR) upper spacer contact points

• Any atypical conditions

• If applicable, debris filter LTP visual exam - for trapped debris and crud buildup

• The side identification convention on the photographs reflects the GE designations of sides 3 & 4 adjacent to the control blade with 1 & 2 away from the CB. Sides 1 through 4 advance in a clockwise direction.

Individual Rod

• LEP serial number & weld

• Oxide levels & characteristics; Visual Standard (VS) rating; any crud or oxide spalling

• Spacer contact areas

• Cladding surface layer (oxide) thickness and diameter characterization by visual and Eddy Current (EC) liftoff measurements and profilometry (COINS)

• Any atypical observations 5

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Figure 1. JYK690, GE14i, -20 GWd/MTU, Bundle Observations

(( ((

)) ))

Side 4,161", UEP-(( )) on right end Side 4,155", (( ))

(( ((

)) ))

Side 2,85", Mid-tier in unbrushed condition Side 4,59", Mid-tier between 3rd and 4th spacers

(( ((

)) ))

Side 1, 55", 3rd spacer Side 4, 7", Transition area (( ))

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Figure 2 JYK690, GE14i, -20 GWd/MTU, Individual Fuel Rod Observations

(( ((

)) ))

(( )) 100", Mid-tier between 5th and 6th spacers (( )) 95", PLR UEP

(( ((

)) ))

(( )) 92", 5th Spacer, Spring contact (on PLR) - typical (( )) 92", 5th Spacer, Spacer spring contact - typical

(( ((

)) ))

(( )),85", Mid-tier between 4th & 5th spacers (( )), 73", 4th Spacer contacts - typical 7

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Figure 3 JYK690, GE14i, 20 GWd/MTU, Individual Isotope (Co-60) Rod Observations

(( ((

)) ))

(( )) 160", UEP (segmented rod) (( )) 121", 7th Spacer contact mark - typical

(( ((

)) ))

(( )) 73", 4th Spacer, Two segments joining area (( )) 55", 3rd Spacer spring contact - typical

(( ((

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(( )) 17", Hex region just below 1st Spacer (( )) 5", part of rod serial number 8

ATTACHMENT 4 Clinton Power Station EOC13 COmbined INStrumentation Measurement System (COINS) Data Report, Measured December 2011 -

Non-Proprietary

Global Nuclear Fuel AJoint Venture of GE. Toshiba. & Hitachi 0000-0 145-1983-N P eDRF Section 0000-0145-1983 March 2012 Non-Proprietary Information - Class I (Public)

Fuel Examination Services COINS Data Field Test Report Clinton Power Station EOC13 COmbined INStrumentation Measurement System (COINS)

Data Report Measured December 2011 Copyright 2012 Global Nuclear Fuel- Americas, LLC All Rights Reserved

0000-014S-1983-NP Non-Proprietary Information - Class I (Public)

FUEL EXAMINATION SERVICES FIELD TEST REPORT

_._._I________._

(

Reference:

PR121-01)

.._m~-r-~---------. .

TITLE: Clinton Power Station EOC 13 COmbined INStrumentation Measurement System (COINS) Data Report DATE: December 2011

,...".tidBy: tfif1t-.~ r FUIII"'~

_._____________ w~-.-------------.

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PROPRIETARY INFORMATION NOTICE This is a non-proprietary version of the document 0000-0145-1983-P, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )).

IMPORTANT NOTICE REGARDING CONTENTS OF TillS REPORT PLEASE READ CAREFULLY The only undertakings of Global Nuclear Fuel-Americas, LLC (GNF-A) with respect to information in this document are contained in contracts between GNF-A and its customers, and nothing contained in this document shall be construed as changing those contracts. The use of this information by anyone other than those participating entities and for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF-A makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.

This document records technical information status at the date of publication and may not represent final disposition or conclusion related to the reported study. Changes in test data, analytical models, and evaluations subsequent to publication of this document may supersede the reported work and verification of applicability should be made before results are used in final design work.

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1.0 INTRODUCTION

Global Nuclear Fuel-Americas (GNF-A) Fuel Examination Services (FES) performed an irradiated fuel examination in December 2011 of a fuel assembly that included dimensional characterization of a selection of both segmented isotope rods and standard fuel rods from one GE14i (isotope) bundle. The bundle, isotope and fuel rods that were examined and measured are identified in Table 1. The rods chosen for exam were a standard array of high duty, low duty, Gadolinium, and part length rods as well as rods in close proximity to segmented isotope rods. The measurements were performed using the COmbined INStrumentation Measurement System (COINS). This Field Test Report presents the results of the individual rod measurements. Table 2 lists the fuel bundle number and rod lattice location with calculated oxidelliftoff (RALO - Rod Average Liftoff and MELO - Maximum Effective Liftoff) values from axial averaging techniques associated with each COINS measurement.

Summary of Results: The fuel rods exhibited small amounts of liftoff/oxide layer with a corresponding normal 00 profile. The segmented isotope rods exhibited negligible amounts of liftoff/oxide layer with a corresponding normal 00 profile, but subject to changes from segment to segment due to different tubes used in manufacture. The fuel and segmented isotope rod performance is excellent and is well within the GNF fuel performance experience base for liftoff/oxide (Figure 3).

A description of the COINS measurement system and how the data are processed is included along with definitions of system accuracy and repeatability. The appendices contain plots of the COINS surface layer (oxide/liftoff) thickness and clad outside diameter (00) profilometry data.

2.0 COINS SYSTEM DESCRIPTION COINS measures some dimensional characteristics of individual fuel rod cladding. COINS consists of two eddy-current (EC) probe lift-off instruments to measure the waterside oxide /

corrosion thic~ness plus tenacious surface crud on the cladding (surface layer thickness) and two surface contacting lateral displacement probes to measure the axial 00 profile (profilometry with a(( )) sensor) of the cladding plus oxide and tenacious surface crud. Axial liftoff measurements are performed at two azimuthal orientations 180 deg apart (designated as

'left probe' and 'right probe') during each scan. ((

))

Four axial traces, two oppOSing pairs, are generated for each rod measured, resulting in three data sets (liftoff on left and right side and overall clad 00 profile). ((

Page 1

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)) Figure 1 shows the bundle facing side of the rod with respect to the probe designations.

Side 4 ABC 0 E F G H J K r

1 2

3 4

Side 5 Side 3 1 6

7 8

9 0

Side 2 COINS 0 deg Orientation Fuel Rod Profilometer and Lift-off Left Probe Profilometer and Lift-off Right Probe Side 2 Profilometer and Lift-off Left Probe Profilometer and Lift-off Right 4

Figure 1. COINS Measurement Orientation Page 2

0000-0145-1983-NP Non-Proprietary Information - Class I (Public) 3.0 COINS SURFACE LAYER THICKNESS MEASUREMENT Surface layer thickness measurements are made using the eddy current lift-off method. Eddy current (EC) signals from spring loaded probes riding on opposing sides of the fuel rod being measured (defined as left and right) are collected at high frequency ((( ))) and low frequency ((( ))) using GNF's DASAR (Data Acquisition Storage And Retrieval which uses a (( )) for EC operation) system. ((

))

Each axial translation or run passes the lift-off probes over the calibrated COINS standard at the bottom of the fuel rod. A program uses data from the standard to convert lift-off voltages into surface layer thickness, dimensioned in mils or microns. Data collected are reviewed for the presence of significant ferromagnetic crud. The program can also apply a correction factor to adjust the lift-off values for the confounding effects of ferromagnetic crud when present.

Significant ferromagnetic crud is considered to be present when the surface layer thickness values differ from the uncorrected values by more than (( )). All charts show uncorrected (red line) and corrected (green line) plots. All MELO data reported in Table 2 are reported as stated in the GNF lift-off summary database. Results of the data reduction of oxide/liftoff are shown in Appendix B. Note that the traces for segmented isotope rods indicate spikes at the transitions between segments, which are threaded connectors with hexagonal flat features. The spikes in the plot are expected and not an abnormality or defect in the rod.

The same COINS standard was used to calibrate the lift-off measurement. ((

))

Random error sources ((

))

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0000-0145-1983-NP Non-Proprietary Information - Class I (Public) 4.0 COINS PROFILOMETRY MEASUREMENT COINS dimensional rod scans include collection of data from the 00 profilometer portions of the calibration standard for every fuel rod scan. These measurements are recorded from a ((

)) contact sensor that produces an overall diameter of the fuel rod cladding, oxide, and adherent crud. ((

)) Results of the data reduction of 00 by profilometry are shown in Appendix A. Note that the traces for segmented isotope rods indicate spikes at the transitions between segments, which are threaded connectors with hexagonal flat features. The profilometry measurement requires smoothly functioning surfaces on the COINS instrument head of the slides, sensor bar, and sensor block. The spikes in the plots are expected and not an abnormality or defect in the rod.

5.0 RELATIONSHIP OF MEASURED QUANTITIES Figure 2 diagrams the relationships of the Cladding 10, Cladding 00, total 00 including surface layer thickness (oxide plus adherent crud). When COINS collects data, it measures each of these variables independently and with different techniques. It does not compute or combine any variables using other measured values. Each measurement technique integrates the area being measured differently and precise comparisons should not be expected. Comparative computations may be performed during analysis of these data as a check for consistency.

Regional diameter increases may be due to crud deposits that should also show up as increased liftoff.

COINS SURFACE LEFT

'LIFT OFF' Page 4

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Table 1. Clinton COINS Exam Population Bundle Rod

((

))

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Table 2 Clinton EOC 13 RALO and MELO Calculated Values 1 ROD_RUN RALO (mils) MELO (mils) RALO (microns) MELO (microns)

))

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Figure 3. Clinton 2011 Liftoff Measurements vs Experience Base

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Appendix A COINS PROFILOMETRY DATA JYK690 Page A-I

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Appendix B COINS OXIDE DATA JYK690 Page B-1

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