ML20083P783

Nonproprietary Third Cycle Performance of Beaver Valley Unit 1 Fuel. Info Deleted

ML20083P783
Person / Time
Site:	Beaver Valley
Issue date:	03/31/1984
From:	Murtha J, Schmidt G WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19268E817	List: ML20083P757 ML20083P763 ML20083P768 ML20083P783
References
WCAP-10494, NUDOCS 8404200164
Download: ML20083P783 (56)

Text

'

WESTINGHOUSE PROPRIETARY Cl. ASS 3 l

! I l WCAP-10494 l Third Cycle Performance of Beaver Valley Unit 1 by J. E. Murtha G. R. Schmidt March 1984 Approved:

E. Roberts, Manager Irradiation Testing 8404200164 840409 P

PDR ADOCK 05000334 ,

PDR

Westinghouse Electric Corporation Nuclear Energy Systems P.O. Box 355 1059L:6/840301 PittsburEhn PA 15230 J

i WESTINGHOUSE PROPRIETARY CLASS 3 l Table of Contents Section Title Page 1 Introduction 1-1 2 Beaver Valley Unit 1 Fuel Design 2-1 3 Beaver Valley Unit 1 Third Cycle 3-1 Operating History 4 Fuel Examination 4-1 4.1 Binocular Examination 4.2 Television Examination 4.2.1 Standard 17x17 Region 3 Fuel Assemblies 4.2.2 Standard 17x17 Region 4 Fuel Assemblies 4.2.3 Baffle Joint Fuel Assemblies 4.2.4 Peripheral Fuel Rod Channel Closure 4.2.5 Peripheral Fuel Rod-to-Nozzle Gap and Rod Growth 4.3 Fuel Assembly Length Measurements

. 5 Conclusions 5-1 6 References 6-1 Appendix A Appendix B iii 1059L:6/840206

1 i

WESTINGHOUSE PROPRIETARY CLASS 3 List of Illustrations

(

Figure Title Page 3-1 Cycle 3 Core Loading Pattern 3-3 3-2 Cycle 3 Coolant Activity 3-4 3-3 Boron Versus Lithium Concentration in DLW's Reactor Coolant During Cycles 1, 2, and 3 3-6 4-1 Surface Condition of Peripheral Fuel Rods in Beaver Valley Fuel Assembly C49. Left Side EOC-2, EOC-3 4-6 4-2 Location of Fuel Assemblies Examined for Effects

! of Coolant Cross Flow Through Baffle Joints 4-13 4-3 Example of White Clean Mark on Grid 6 on Face 3 of Assembly E43 4-15 4-4 Maximum Channel Closure [ ] Percent, Fuel Assembly C06, (b,c) face 4, span 3, rods 5-6 4-18 4-5 EOC-3 Axial Variation in 95th percentile Peripheral Fuel Rod Channel Closure in Beaver Valley Unit 1 4-19 4-6 Worst-Span Channel Closure Behavior at the 95th Percentile Level 4-20 4-7 Bottom Gap Change Versus Burnup 4 4-8 Top Gap Change Versus Burnup 4-24 4-9 Fuel Rod Growth Variation With Fluence 4-27 i

'l v

1059L:6/840220 ]

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WESTINGHOUSE PROPRIETARY CLASS 3 List of Tables Table Title Page 2-1 Core Design and Operating Characteristics 2-2 3-1 Power and Burnup History Summary for Beaver Valley Unit 1 3-2 4-1 Beaver Valley EOC-3 Binocular Examination of Assemblies 4-2 4-2 Beaver Valley Unit 1 Planned EOC-3 TV Visual Examination - Region 3 4-5 t

4-3 Beaver Valley Unit 1 Planned EOC-3 TV Visual Examination - Region 4 4-10 4-4 Beaver Valley Unit 1 Cycle 3 Baffle Joint Assemblies Examined 4-12 4-5 Beaver Valley Unit 1 Cycle 3 Baffle Joint Assemblies Exhibiting Minor Baffle Joint Cross Flow Spraying 4-14 4-6 Fuel Rod Channel Closures > [ ] Percent in (b,c)

Beaver Valley Unit 1 Fuel at EOC-3 4-16 4-7 Summary of Fuel Rod-to-Nozzle Gap Data 4-22 4-8 Summary of Beaver Valley Unit 1 Cycle 3 Assembly Growth Data 4-28 vif 1059L:6/840220

WESTINGHOUSE PROPRIETARY CLASS 3

1.0 INTRODUCTION

The 17x17 fuel assembly is in extensive operation in recent Westinghouse l 3-loop and 4-loop reactors with power up to 3800 MWT and average linear power of approximately 5.3 kw/ft. This design extends fuel capability beyond that of the 15x15 design in use to date in reactors of this size. It was adopted primarily in response to the lowered average kw/ft requirements imposed by the AEC Interim Acceptance Criteria. While the primary intent of the design h to reduce stored energy in fuel rods for LOCA conditions, it is also expected that rod bow will be decreased because of the shorter grid span lengths characteristic of the 17x17 design.

The NRC has required that fuel surveillance inspections be performed on the first several 17x17 plants to go into operation, including Beaver Valley Unit 1, to verify satisfactory fuel performance.

The purpose of the Beaver Valley fuel examination was to evaluate the mechanical integrity of fuel rods and fuel assembly structural components, fuel surface condition, rod-to-nozzle gap and fuel rod bow, and to compare the Beaver Valley fuel performance with that of other 17x17 fuels.

Beaver Valley Unit I completed Cycle 1 in November, 1979. Thirty-five fuel assemblies were non-destructively examined with underwater television and a large number of assemblies were binocular examined. The visual examination showed the assemblies to be in excellent mechanical condition.(I)

Cycle 2 of Beaver Valley Unit I was completed in December, 1981. One hundred fifty-three (153) fuel assemblies were binocular examined and thirty (30) fuel assemblies were TV visually examined with underwater television consistent with the planned program. Of the thirty fuel assemblies, ten fuel assemblies were selected as representative fuel assemblies from Regions 2 and 3 and the remaining twenty fuel asse:::blies were examined for possible effects of coolant cross flow through baffle joints. In addition, several assemblies, supplementary to the planned program, were examined due to fuel handling problems.(2)

I l-1 1059L:6/840206 i

WESTINGHOUSE PROPRIETARY CLASS 3 Cycle 3 of Beaver Valley Unit I was initiated on July 8,1982, and was completed on June 10, 1983. The Beaver Valley End-of-Cycle 3 Fuel Inspection Program was initiated on July 2,1983, and completed on August 5,1983. One hundred fifty-seven (157) fuel assemblies were binocular examined during unloading from the core. TV visual examination was performed on twenty (20) standard 17x17 Region 5 fuel assemblies which operated adjacent to the baffle during Cycle 3, five (5) standard 17x17 Region 3 fuel assemblies, two (2) demonstration 17x17 optimized fuel assemblies, and four (4) standard 17x17 Region 4 fuel assemblies. In addition, fuel assembly length measurements were taken on sixty (60) assemblies.

This report presents the results of the examination of standard fuel assemblies at the End-of-Cycle 3. Results of the inspections related to the optimized fuel demonstration assemblies will be reported separately.

l 1-2 1059L:6/840206 1

WESTINGHOUSE PROPRIETARY CLASS 3 2.0 BEAVER VALLEY UNIT 1 FUEL DESIGN Duquesne Light, Beaver Valley Unit 1 is a 3-loop 17x17 reactor with 2652 MW thermal power rating. The fuel in Beaver Valley Unit 1 is of the low parasitic design. Each of the 157 fuel assemblies in the reactor core contains 264 Zircaloy-4 clad fuel rods. Each rod is approximately thirteen feet long and contains a twelve-foot long column of fuel pellets. Spacing between the fuel rods is maintained by eight Inconel 718 alloy grids nearly equally spaced along the length of the fuel rods. In each fuel assembly, the top and bottom nozzles and the eight grids are attached to twenty-four Zircaloy-4 thimble tubes which extend between the nozzles and through the eight grids. In the Region 5 fuel, pellet density was 95 percent of theoretical density, and the fuel rods were prepressurized with helium to [ ] psig. In Table 2-1, several Beaver Valley Unit 1 core design (a,c) and operating characteristics are compared with those of Salem Unit 1 (Public Service Electric and Gas Co.), and Trojan (Portland General Electric Company) reactors.

While physical dimensions of the Beaver Valley Unit 1 fuel are the same as in the standard 17x17 design in the Salem Unit 1, Salem Unit 2 and Tro,ian reactors, the nuclear and thermal characteristics are not identical. Core

- average linear power is lower in Beaver Valley than Trojan ar.d both Salem units.

2-1 1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 TABLE 2-1 CORE DESIGN AND OPERATING CHARACTERISTICS Sal ;.. l Beaver Valley Salem -

Unit 1 Unit 1 Unit 2 Trojan )

i U02 Enrichment w/o U-235 Region 1 (a,c)

Region 2 Region 3

) Region 4 Region 5

. Coolant Temperature Hot Zero Power, *F Initial Inlet Initial Core Ave.

HFP, *F Operating Coolant Pressure, psig Average Linear Power kw/ft i

i

~

1059L:6/840206

l l

i WESTINGHOUSE PROPRIETARY CLASS 3 l l

l l 3.0 BEAVER VALLEY UNIT 1 THIRD CYCLE OPERATING HISTORY Beaver Valley Unit 1 achieved criticality in the third cycle in July,1982 and completed the third cycle in June, 1983 with Cycle 3 average burnup of 10,637 MWD /MTU. A brief summary of res;on burnup and powers is given in Table 3.1.

The Cycle 3 core loading pattern is given in Figure 3-1.

The activity of the fission products I-131 and I-133 in the primary coolant was measured during Cycle 3 to monitor the defect condition of the fuel.

Iodine activity is an important indicator of fuel integrity. Although there is no quantitative correlation of activity with the number of fuel rod defects, because large defects release more activity than small defects and because reactor power transients cause sudden transient activity increases or spikes, activity levels in a general sense reflect the condition of the fuel.

The I-131/I-133 activity ratio is an indicator of the type of defect. A low I-131/I-133 ratio results from an open fuel rod defect, one which allows rapid release into the coolant of both the longer half life I-131 and the shorter half life I-133. A closed defect restricts release of iodine from the fuel rod and since the short-lived I-133 decays to Xe 133 more rapidly than does the I-131, the ratio of I-131 to I-133 in the coolant is higher. A ratio of 0.1 to 0.3 indicates rapid release through an open defect, and a ratio greater than 0.5 indicates delay of iodine release through a tight defect. Figure 3-2 shows the activity in the coolant during Cycle 3. All iodine measurements reported here were made at or near full power, thus avoiding transients or spikes associated with increasing or decreasing power.

Cycle 3 began with a coolant activity of ~3x10 -3p Ci/g I-131 with an I-131/I-133 ratio of ~ 0.25. The coolant activity level was essentially unchanged from the end of cycle 2; however, the ratio was considerabl; lower than the E0C 2 Iodine ratio of 0.6. This decrease in ratio indicates removal.

of some fuel rods with tight defects at EOC 2. The BOC three I-131 level indicates the presence of a few rods with more open defects. Additional rods defected during Cycle 3 indicated by an increasing I-131 activity level to 9x10-3u Ci/g with a constant Iodine ratio through March. These defects are also of an open type.

3-1 1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 TABLE 3-1 Power and Burnup History Summary for Beaver Valley Unit 1 Cycle 1 Cycle 2 Cycle 3 Average Power Burnup Average Power Bu rnup Average Power Burnup Realon _ _( kw/ft) (HWD/HTul (kw/ft) (HWD/HTU) (kw/ft) (HWD/HTut 1 -

(a.c) 2 3

4 4a W

~ _

1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 7905-1 180*

R P N M L K J H G F E D C D A E03 E21 E24 1 i.

E38 E40 E02 E49 E10 E33 2 E34 E29 2 C46 C22 W M7 E31 E20 3 J2 K 12 H-4 F 12 G2 E23 C32 DU C01 D36 C07 D31 C3 m CM E-01 4 A44 L3 G 11 L2 H-7 E2 J 11 E3 D-4 D16 C30 D03 C13 D19 C48 D22 C23 D11 5 E37 E18 E12 EM N4 J-7 J1 J-4 H1 G-4 G1 G7 C-5 E43 E38 6 P-7 E9 R7 K-6 M-3 H-6 D-3 F-6 A7 L-9 B-7 C06 D35 C27 D21 C49 D38 C14 D01 C51 043 C04 7 D-6 P5 M-7 N-4 L-5 K2 E5 C4 D7 8-5 M4 1 00 A26 D34 C17 202 CO3 CU DN 30 8 E11 E47 8 210" P 10 M-8 J-8 R-8 K8 P-6 M4 86 F4 A-8 G-8 D-8 B 10 EOS De M W2 C43 DM d2 N C26 E41 E27 8 E22 D-10 P 11 M-9 N 12 L 11 K 14 E 11 C 12 D-9 s-11 M 10 E44 C18 DIO C37 D14 CM D24 Q4 m CW N E46 10 P-9 E7 R-9 K 10 M-13 H-10 D 13 F 10 A4 L7 89 D44 C29 D13 C44 D17 C10 DOS C11 D49 99 N 11 J-9 J-15 J-12 H 15 G-12 G 15 G9 C 11 19 D26 C15 D4 M E18 EOS 12 M-12 L 13 G-5 L 14 H-9 E-14 J-5 E 13 D-12 g E17 E26 E25 E13 13 J 14 K-4 H-12 F-4 G 14 E39 E30 E48 E28 E14 Ett 14 E07 EOS E15 15 0'

REGIDN 4A (3 2 w/ol A REGION 112.1 w/o) ZD OPTIMlZED FUFL FACE 4 es -

C REGION 3 (31 w/ol E REGION 5 (3.0 w/ol l

m a REGION 4 (3 J .v/ol FACE 2 D STANDARD FUEL XXX ASSEMsLY IDENTIFICATION Figure 3-1 Cycle 3 Core Loading Pattern 3-3 l

1E+00 1 E-01 -

a N /' / m e m 5 i[ 1E-02 -

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JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL DATE Figure 3-2 Beaver Valley-1 Cycle 3 Coolant Activity 8

WESTINGHOUSE PROPRIETARY CLASS 3 Further defect formation events occurred in March through May with the I-131 activity level increasing to 2x10-2p C1/g and I-131/I-133 ratio of

~ 0.5. The increased Iodine ratio indicates these later defects are of a different nature and are tight defects.

Figure 3-3 shows boron-lithium concentration for Cycles 1, 2, and 3. Beaver Valley operated in a crud dissolving mode for all three cycles. The critical solubility curve of Figure 3-3 represents the dividing line between crud precipitating and crud dissolution based on the crud transportation processes developed by Westinghouse.(3) Below the solubility curve, there is a tendency for magnetite precipitation on hotter surfaces, assuming a saturated ~

solution. Above the curve, the solubility of magnetite increases with temperature; thus there should be a tendency to dissolve the material from the core surface, or at least to retard the precipitation.(4) 1 1

3-5 1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 2485-5 l

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2.5 LEGEND

O EOC-1 O EOC-2 N 6 EOC-3 2.0

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\ WESTINGHOUSE

\ RECOMMENDED BORON /

\ LITHIUM CONCENTRATION 1.5 -

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FOR ZERO TEMPERATURE COEFFICIENT C--

OF SOLUBILITY AT 285 C 0.5 -

0.0 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 ppm B Figure 3-3 Boron Versus Lithium Concentration in DLW's Reactor Coolant During Cycle 1, Cycle 2 and Cycle 3 1

3-6 l

WESTINGHOUSE PROPRIETARY CLASS 3 4.0 FilEL EXAMINATION At the end of Cycle 3, Duquesne Light Company and Westinghouse performed a Fuel Inspect'or Program. The Beaver Valley End-of-Cycle 3 Fuel Inspection Program was initiated on July 2, 1983 and completed on August 5, 1983. This inspection included a binocular visual examination of every fuel assembly which operated in Cycle 3, TV visual exam of twenty (20) standard 17x17 Region 5 fuel assemblies which operated adjacent to the baffle during Cycle 3, TV visual exam of five (5) standard 17x17 Region 3 fuel assemblies, TV visual exam of two (2) demonstration 17x17 optimized fuel assemblies, and TV visual exam of four (4) standard 17x17 Region 4 fuel assemblies. Also included in the program were fuel assembly length measurements on sixty (60) fuel assemblies and fuel rod breakaway withdrawal force measurements on twenty (20) fuel rods from the demonstration assemblies.

4.1 Binocular Examination Every fuel assembly which operated in Cycle 3 of Beaver Valley Unit 1 (listed in Table 4-1) was examined with binoculars during unloading from the core. As the assemblies were transferred from the upender to their storage rack locations in the spent fuel pool, each was stopped momentarily and rotated so all four faces could be examined.

The binocular examinations indicated that the assemblies were in good mechanical condition with no visible damage to any fuel rods or structural components. Occasionally, shiny areas on a grid could be seen where the crud l was scratched off during removal from the core. However, no damage to a grid was observed on any assembly.

Crud on the assemblies appeared to be very thin and no unusual corrosion was observed. The crud was distributed uniformly on the assemblies and did not appear to vary along its length, or from assembly face to face. Typically, the color of the crud ranged from a medium grayish brown for the one cycle assemblies to a darker gray for the three cycle assemblies.

1059L:6/840206 4-I L

i WESTINGHOUSE PROPRIETARY CLASS 3

! TABLE 4-1 Beaver Valley EOC-3 Binocular Examination of Assemblies i

Region 1 Region 3 Region 4 Region 4a Region 5

A26 C01 001 ZD1 E01 CO2 002 ZD2 E02 C03 003 E03 C04 004 E04 C05 DOS E05 C06- D06 E06 C07 007 E07 C08 D08 E08 C09 009 E09

C10 D10 E10 C11 011 Ell

. C12 012 E12 C13 D13 E13 C14 D14 E14

! CIS D15 EIS C16 D16 E16 C17 D17 E17 C18 D18 E18 C19 D19 E19 C20 D20 E20 C21 D21 E21 C22 D22 E22 C23 D23 :E23

C24 D24 E24 C25 D25 E25 C26 026 E26 i C27 D27 .E27 C28 D28 E28~

(.

C29 D29 E29 C30 030 E30

'C31 D31' E31 C32 D32 E32 C33 D33 E33 C34 D34 E34

, C35 035- E35 C36 036 E36 C37 D37 E37 l C38 D38 E38 C39 D39 E39 C40 D40- E40 l C41- D41 .E41 l C42 042 E42 C43 D43 E43 h

l 1059L:6/840206

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WESTINGHOUSE PROPRIETARY CLASS 3 1.

4 TABLE 4-1 (cont) 1 Region 1 Region 3 Region 4 Region 4a Region 5 C44 D44 E44 j C45 D45 E45 C46 D46 E46 C47 047 E47 C48 048 E48 C49 D49 E49 C50 050 E50 C51 E51 CS2 E52 1

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s Fuel rod bow was observed to be minigal, witt. only occasional channePclosures u s greater than [ ~ ] observed on an individual assembly. The nuabar of (a,c) large channel cTosures,[ ] were more numerous on assemblies with three (a,c) cycles of burnup and 'decrea' sed progressively for the two and one cycle n.

assemblies, respectively. The large channel ' closures were ly:ated mostly in the bottom three spans of an assembly. There were no cises of complete .

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4.2 Television Examination: General Fuel Conditiqn T' ,

v i The low magnificatioitelevision examination was a full face euninatkon of^

all fuel assembly faces from the bottom nozzle to the top nozzle. Each fuel g

assembly was positioned in front of the te19 vision camera so that ghe field '

view covered a 3x4 inch area of the assembly face. The assembly was lowered or raised in front of the television camera, scanning from nozzie to nozzle.

The left half of the assembly face was examined in the first r,can,. and the s i  %

right half of the face was examined in the second scan. Routinely 3 each scan was halted, briefly, at the b5ttom and top nozzle, at each grid and a't e'ach mid-span position between grids.( ) '

s i

4.2.1 Standard 17x17 Region 3 Fuel Assemblies -

3 Five (5) standard Region 3,17x17 fuel assemblies (listed in Table 4-2) were examined at low magnification. All of the assemblies were in good condition following three cycles of operation. No unusual fuel performance character-istics or mechanical damage was observed on any cf the assemblies. The sur-face condition of peripheral fuel rods for assembly C49 is shown'in figure 4-1.

4.2.2 Standard 17x17 Region 4 Fuel Assemblies Four (4) Region 4 fuel assemblies (listed in Table 4-3) were examined with TV at low magnification because of handling incidents and possible unusual conditions. It was recommended by Westinghouse that these assemblies be video examined prior to use in subsequent cycles. These assemblies were examined and found to be in good condition.

1059L:6/840206 {

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WESTINGHOUSE PROPRIETARY CLASS 3 .

TABLE 4-2 Beaver Valley Unit 1 E0C-3 TV Visual Examination Region 3 '

Fuel Core Assembly No. Location Comment C03 D08 Examined at E0C-1, EOC-2 C06 N07 Examined at E0C-1, E0C-2 C15 F12 Examined at EOC-1, E0C-2 C39 N08 Examined at EOC-1, E0C-2 C49 J07 Examined at E0C-1, EOC-2 i

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F Figure 4-1 Surface Condition of Peripheral Fuel Rods in Beaver Valley Fuel Assembly 8 C49 Face 3 Left Side EOC-2 and EOC-3 (Sheet 1 of 4) $

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Figure 4-1 Surface Condition of Peripheral Fuel Rods in Beaver Valley Fuel Assembly $

C49 Face 3 Left Side EOC-2 and EOC-3 (Sheet 3 of 4) 8 -

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UESTINGHOUSE PROPRIETARY CLASS 3 TABLE 4-5 Beaver Valley Unit 1 Cycle 3 Baffle-Joint Assemblies Exhibiting Minor Baffle-Joint Cross Flow Spraying Fuel Core Assembly No. Location E40 K02 E34 M03 E43 P06 E14 F14 E46 B10 E36 B06 e

4-14 1059L:6/840206

1 WESTINGHOUSE PROPRIETARY CLASS 3 8050-5 l

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WESTINGHOUSE PROPRIETARY CLASS 3 TABLE 4-6 Fuel Rod Channel Closures [ ] Percent in (a,c)

Beaver Valley Unit 1 Fuel at E0C-3 Fuel Assembly No. Face Span Rod EOC-1 EOC-2 EOC-3 CIS (b,c)

C39 4

C49

C03 1

I C06 I

4-16 1059L:6/840206 - .

WESTINGHOUSE PROPRIETARY CLASS 3 L (a,c)-

M = spacing between two adjacent fuel rods a't mid-span location between grids j T = spacing between two adjacent fuel rods at the top of the grid span B = spacing between two adjacent fuel rods at the bottom of the grid span

! The largest closure observed at the end-of-cycle 3 was [ ] (b,c)

[ ] percent. This was the channel closure between rods 5 and 6, span 3, (b,c) face 4, of fuel assembly C06. The closure is shown in Figure 4-4. .This j channel was [ ] percent closed at EOC-1, and [ ] percent closed at EOC-2. (b,c)

The axial variation of channel closure in each region is shown in Figure 4-5.

! The span 1 closure in Figure 4-5 has been normalized to' compensate for the l longer length of the first span (24 inches in span 1 and 20 inches in the upper span). The closure in span 1 was normalized by the ratio

(2 )2 . (This is derived from the ratio of flexural rigidity (I/1)2 between 24-inch-span and 20-inch-span). The worst _ span closure

occurred in span 1 for the Region 3 assemblies measured as can be seen in l Figure 4-5. Figure 4-6 shows the 95th percentile closure in the worst-axial

grid span of Beaver Valley Unit 1 at EOC-1, EOC-2 and EOC-3 as well as Surry i 7 grid 17x17 assemblies, Trojan 8 grid 17x17 asseeblies and Salem 8 grid 17x17 assemblies. The rod bow design limit curve approved by the NRC is also j shown. The Surry data.(7 grid) have been normalized to the'same length as the 8 grid standard 17x17 fuel in other. reactors. As seen in Figure 4-6, Beaver Valley Unit 1 closures are well below the design curve for the 8 grid 17x17 J

design and consistent with other data.

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WESTINGHOUSE PROPRIETARY CLASS 3 80504

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Figt.re 4-4 Maximum Channel Closure [ ] Percent, Assembly (b,c)

C06, Face 4 Span 3 between Rods 5 and 6 4-18

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WESTINGHOUSE PROPRIETARY CLASS 3 4.2.5 Peripheral Fuel Rod-To-Nozzle Gap and Rod Growth The axial gap between peripheral rod and assembly nozzle for five (5) assemblies, C03, C06, CIS, C39, and C49 was measured from the low magnification image on the television video tapes.

The low magnification television measurements of rod-to-nozzle gaps were calibrated for each fuel assembly face by measuring the video tape image of several grid springs on the outside straps in the top grid and bottom grid.

The spring slot lengths on the top grid, on each individual face, were averaged and used as the standard for the top rod-to-nozzle gap measurements on that face. Similarly, the spring slot lengths from each bottom grid were averaged and used as a standard for the bottom rod-to-nozzle gap measurements I on that face.

I Appendix B contains the fuel rod-to-nozzle data for each of the five (5). ,

assemblies that had measurements taken. A summary of these results is found in Table 4-7. The average bottom gap for Region 3 was [ ] inches, and (b,c) the average top gap for Region 3 was [ ] inches. The average total gap (b,c) for Region 3 was [ ] inches. (b,c) ,y 4

The average percent change in bottom gap for Region 3 was [ ] percent, (b,c) (

with a minimum of [ ] percent and a maximum of [ ] percent. (b,c)

Figure 4-7 shows percent change in bottom gap as a function of burnup fo'r the -

five (5) Region 3 fuel assemblies from which data were obtained. Figure 4-7 also includes data from other plants as well as the data from Beaver. Valley Unit 1, end-of-cycle 2. It can be seen from Figure 4-7 that the bottom; gap decreases continuously with burnup.

The average percent change in top gap for Region 3 was [ ] percent, with (b,c) a minimum of [ ] percent and a maximum of [ ] percent. Figure 4 (b,c) shows percent change in top gap as a function of burnup for the five(5) Region 3 fuel assemblies from which data were obtained. Figure 4-8 also includes data 1059L:6/840206

.]

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4 I

WESTINCHOUSE PROPRIETARY CLASS 3 Table 4-7

.  : Summa ry of f ue l Rod-To-Nozzle Gap Data Percent Change Percent Change Percent Change Bottom can Too Cap Total Cao Rod Crowth Botton Cao Too Cao Total Cao Average Region 3 --

(b,c)

MiQiaus Maximum

Ae N

N 1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 3760 100 __

3 3 (b, c)

<3 6 50 -

0 b .

c i 8

z w 0 -

c z

I o

f

! l l

-50 _ -

0 to 20 30 g BURNUP (x 103MWD /MTU) l l

f Figure 4-7 Bottom Gap Change Versus Burnup 4-23

WESTINGHOUSE PROPRIETARY CLASS 3 3760 i

100 3 (b, c) 3

• 1 50 -

d.

C 8

2 m

$ 0 -

I U

-50  !

0 10 20 30 40 3

BURNUP (x 10 MWD /MTU) 1 Figure 4-8 Top Gap Change Versus Burnup 4-24

WESTINGHOUSE PROPRIETARY CLASS 3 4 I from other plants as well as the data from Beaver Valley Unit 1, end-of-cycle

2. It can be concluded from Figure 4-8 that the top gap changes little with burnup through this level of exposure.

The observation of burnup dependent bottom gap, and burnup independent top gap, supports the interpretation that the fuel rods grow predominantly downward until the bottom gap is fully closed. There are occurrences, however, of occasional fuel rod slippage downward through the grids as evidenced by the negative values recorded for the percent change in top gap.

The gap data obtained for the Beaver Valley Unit 1, 3-cycle assemblies indicate that an adequate rod-to-nozzle gap exists to accommodate continued rod growth for further cycles of irradiation.

Fuel rod growth for each rod examined was derived from the rod-to-nozzle gap data and the predicted fuel assembly growth based upon data from other .e s .

Fuel rod growth was derived from the gap measurements using the equation:

A -C Rod Growth = 100 x A= Preirradiation nominal total gap i

B= Irradiation change in nozzle-to-nozzle length (Measured preirradiation nozzle-to-nozzle length times the EOC-3 assembly growth)

C= E00-3 rod-to-nozzle gap D= Preirradiation nominal rod length Fuel rod growth after three cycles of irradiation ranged from [ ] (b,c) percent to [ ] percent with a mean of [ ] percent for Region 3. (b,c)

Individual assembly data is in Appendix B. A summary of the fuel rod growth data is found in Table 4-7.

1059L:6/840206

I WESTINGHOUSE PROPRIETARY CLASS 3 Figure 4-9 plots the combined rod growth data for the five (5) Beaver Valley l Unit 1 assemblies as a function of fast fluence, together with data from several other plants. The Beaver Valley Unit 1, end-of-cycle 3 data are consistent with the data obtained from other plants.

4.3 Fuel Assembly Length Measurements Fuel Assembly length measurements were performed on sixty (60) fuel assemblias (listed in Appendix A) from Regions 1, 2, 3, 4 and 5. The results of the assembly length measurements are also given in Appendix A. A summary of the assembly length data is given in Table 4-8.

The assemblies were found to have grown from [ ] percent to [ ] (b,c) percent larger than their unirradiated nominal fuel assembly length. This is typical for fuel with one to three cycles of irradiation.

t A

i 1059L:6/840206 4-26

WESTINGHOUSE PROPRIETARY CLASS 3 3760

~

101-9 -

8 -

7 -

8 -

' ~

(b, c) 4 -

3 -

2 -

=

5 e

E I1 9 T

$ 8 -

7 -

@ 6 o -

5 -

4 -

3 -

2 -

10-1 I I I I IIII I I I I I I'I 10-1 2 3 4 5 678910 0 2 3 4 5 6789101 2

ASSEMBLY AVERAGE FAST FLUENCE (x 1021 n/cm ) (E > MeV)

Figure 4-9 Fuel Rod Growth Variation With Fluence 4-27 I

L __- _-- _ . . .

WESTINGHOUSE PROPRIETARY CLASS 3 TABLE 4-8 Summary of Beaver Valley Unit 1 Cycle 3 Assembly Crowth Data Fuel Average Growth Growth (%)

Region Assembly No. Burnup (%) Maximum Minimum I

1 Average (b,c) 2 Average 3 Average 4 Average 5 Average 4

1059L:6/840206 4-28

WESTINGHOUSE PROPRIETIRY CLASS 3

5.0 CONCLUSION

S The overall condition of fuel assemblies examined during the Beaver Valley Unit 1, End-of-Cycle 3 Fuel Inspection Program was excellent. Binocular examinations indicated the assemblies were in good mechanical condition with no anomalies observed on any of the fuel rods, grids, nozzles, or holddown springs. TV visual examination of the detected anomalies confirmed these observations. Rod bow for the 1 , 2 , and 3-cycle fuel was typical and minimal. No occurrence of complete channel closure was observed. Crud deposits were thin with no unusual cladding or grid material degradation.

Length measurements indicated fuel rod and fuel assembly growth to be normal.

No obvious baffle joint related damage was observed on the twenty (20) assemblies examined. However, six assemblies showed evidence of slight baffle joint spraying, all of these assemblies appeared to be structurally cound.

Based on the examination performed and the preliminary evaluation of the data, all of the assemblies examined are acceptable for further irradiation.

1

.5-1 1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 REFERENCES

1. W. G. Kotsenas and J. B. Melehan, First Cycle Performance of Beaver Valley Unit 1 Fuel, WCAP-9731, August, 1980.

2. H. Kunishi and P.A. Pritchett, Second Cycle Performance of Beaver Valley Unit 1 Fuel, WCAP - 10196, October, 1982.

3. Solomon, Y. and J. Roesmer, Some Observations on the Possible Relationship-of Reactor Coolant Chemistry and Radiation Level Buildup, WCAP-9407, November, 1978.

4. Sweeton, F.H. and C. F. Baes, Jr., The Solubility of Magnetite and Hydrolysis of Ferrous Ion in Aqueous Solutions at Elevated Temperatures, J. Chem Thermodyn 2, pp. 479-500 (1970).

A j

1 6-1 1059L:6/840305

r .

t WESTINGHOUSE PROPRIETARY CLASS 3 APPENDIX A Beaver Valley Unit 1 Cycle 3 Fuel Assembly Growth l

1 l

l 1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 Beaver Valley Unit 1 Cycle 3 Fuel Assemblies Length Measured

1) E21 31) C32

2) E47 32) 028

3) E10 33) 037

4) E30 34) 047

5) E37 35) 002

6) E05 36) 843

7) ZD1 37) 830

8) ZD2 38) B14

9) 012 39) 835

10) D46 40) 851

11) 025 41) 832

12) 039 42) 813

13) D08 43) 826

14) 045 44) B25

15) D30 45) B38

16) 033 46) All

17) A26 47) B20

18) C17 48) B31

19) C45 49) B07

20) C09 50) B04

21) C21 51) C49

22) C41 52) C15

23) C39 53) A01

24) C26 54) A14 25)6C03 55) A25

26) C06 56) A36 .-

27) C50 57) A10

28) C25 58) A05

29) CO2 59) A20

~ 30).-C05 60) A15 1059L:6/840206

WESTINGHOUSE PROPRIETARY CLASS 3 Beaver Valley Unit 1 Cycle 3 Fuel Assembly Growth Fuel Region Assembly No. Burnup Growth (%)

1 A01 (b,c)

A05 A10 All A14 A15 A20 A25 A26 A36 2 B04 B07 B13 B14 B20 B25 B26 B30 B31 832 B35 B38 B43 B51 1059L:6/840206 A-3 p

_ _ .. . _ _ . . . . _ . . _ _ - _ _ _ _ . _ _ . _ _~ _ _ _ _

WESTINGHOUSE PROPRIETARY CLASS 3 Fuel  !

Region Assembly No. Burnup Growth (%)

3 CO2 (b,c) l C03

. C05 '

i

C06 C09 i CIS C17 C21 -

l C25

C26 C32 i C39 C41

C45 i C49 i C50 4 002

. D08 012 .

025

028 i

D30 D33 037 i'

0,19 ll DL5 D46 047-l i

A-4 1059'.:6/840206 l

i

+

WESTINGHOUSE PROPRIETARY CLASS-3 ,

i  !

+ l 4 .

Fuel  !

1 l Region Assembly No. Burnup Growth (%)

4 j 5 E05 (b,c)

'E10 E21 i E30 i

E37 E47

}

i 3

4 i

l

(

t 1

4 1

I i

i l

4 i

I i

i I

4 1 A-5 i 1059L:6/840206'

WESTINGHOUSE PROPRIETARY CLASS 3 4

l APPENDIX 8 Fuel Rod-To-Nozzle Gap Data l

t B-1 1059L:6/840206

. _ . . _. _ . . - . - _ - _ _ _ _ _ _ - _ -_.___ ___ _ _ -- _ _ _ ..~

i WESTINGHOUSE PROPRIETARY CLASS 3 s

1

! Fuel Assembly C03 1

i Average Minimum Maximum Bottom Gap , (b,c) i Top Gap

Total Gap l

Rod Growth

Percent Change l

i l Bottom Gap i

j Percent Change Top Gap Percent Change

., Total Gap i

t l

l 1

t j i.

f i

e 4

1 1

2 l

i.

B-2 1059L:6/840206 o

. . . . . _ _ _ . _.. - _ , - _ _ , . __ - - ~ -- . . _ _ .,-

I T

WESTINGHOUSE PROPRIETARY CLASS 3 ,

I Fuel Assembly C06 ,

l i

Average Minimum Maximum

, Bottom Gap (b,c) l Top Gap i  ?

j Total Gap i

i

} Rod Growth I .

Percent Change ,

4 j Bottom Gap t

i t'

Percent Change j Top Gap I .

i Percent Change l Total Gap i _._

i

}

1 i

i,  ;

s 4

i i

a l

l i

1 1'

J B-3

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WESTINGHOUSE PROPRIETARY CLASS 3 Fuel Assembly C15 l

Average Minimum Maximum Bottom Gap -

(b,c)

Top Gap Total Gap Rod Growth i

Percent Change L Bottom Gap Percent Change Top Gap Percent Change Total Gap i

sr

)

B-4 I

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WESTINGHOUSE PROPRIETARY CLASS 3 Fuel Assembly C39 Average Minimum Maximum Sottom Gap (b,c)

Top Gap Total Gap Rod Growth Percent Change Bottom Gap Percent Change Top Gap Percent Change

,

• Total Gap i

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WESTINGHOUSE PROPRIETARY CLASS 3 Fuel Assembly C49 Average Minimum Maximum Bottom Gap (b,c)

Top Gap Total Gap Rod Growth Percent Change Bottom Gap Percent Change Top Gap Percent Change Total Gap f

-6 i-1059L:6/840206 l