ML19345B325

Nonproprietary Version of First Cycle Performance of Beaver Valley 1 Fuel

ML19345B325
Person / Time
Site:	Beaver Valley
Issue date:	08/31/1980
From:	Kotsenas W, Melehan J, Roberts E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19262F307	List: ML19345B324 ML19345B325
References
TAC-8595, WCAP-9769, NUDOCS 8011280077
Download: ML19345B325 (39)

Text

{{#Wiki_filter:- WESTINGiOUSE PROPRIETARY CLASS 3 4 8 9; a6 2 FIRST CYCLE PERFORMAfiCE OF BEAVER VALLEY UNIT 1 FUEL by W. G. Kotsenas J. B. Melehan Augus t, 1980 i vf APPROVED: Elwyn Roberts, Manager j Irradiation Testing 4 4 WORK PERFORMED UNDER DGRF-33002 ? .This document is the property of and contains proprietary information owned by the Westinghouse Electric Corporation, Nuclear Energy Systems, and is transmitted to you in confidence and trust and is to be returned upon request. No permission is granted to publish, reproduce, transmit 1 or disclose to another any information contained in this document, in whole or in part, without the prior written permission, in each case, of an authorized employe of said corporation. WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems i P. O. Box 355 Pittsburgh, Pennsylvania 15230 $o / / 2 800 7 7-

i TABLE OF CONTENTS Section Title Pace LIST OF TABLES i LIST OF FIGURE 5 ii 1.0 SCOPE OF REPORT 1

2.0 INTRODUCTION

l 3.0 BEAVER VALLEY UNIT 1 FUEL DESIGN 2 4.0 BEAVER VALLEY UNIT 1 FIRST CYCLE OPERATING l HISTORY 3 i 5.0 FUEL EXA'tINATION 3 5.1 Binocular Examination 4 5.2 Television Examination 4 5.2.1 Televisian Examination--General Fuel Condition 4 5.2.2 High Magnification Television Examination-- 6 Peripheral Fuel Rod Channel Closure 5.2.3 Examination of Fuel Assemblies at Baffle Joints 9 ts. 0

SUMMARY

10

7.0 REFERENCES

10 I \\

\\ LIST OF TABLES l Table Title Page 1 Core Design and Operating Characteristics 11 2 Scope of Beaver Valley Unit 1 EOC-1 Planned 12 Fuel Examination 3 Beaver Valley Unit 1 E0C-1 Fuel Examination, 13 Assemblies Adjacent to Center Injection Baffle Joints 4 EOC-1 Peripheral Fuel Rod Channel Closures in 14 Beaver Valley Unit 1 Fuel Assembly B-13 5 E0C-1 Peripheral Fuel Rod Channel Closures in 15 Beaver Valley Unit 1 Fuel Assemblies I i

1 LIST OF FIGURES Figure Title Page 1 Cycle 1 Power History 19 2 Coolant Average Temperature History 20 3 E0C-1 Power and Burnup of Beaver Valley 21 Unit 1 Fuel Assemblies 4 Time Averaged, Radial-Averaged Power Profile 22 5 lodine Activity in Beaver Valley Unit 1 23 Coolant During Cycle 1 6 Reflective Surface of Rods in Bottom Spans 24 7 Typical Patchy Crud in Fuel Assembly Spans 25 3 and 4 8 Typical Non-Reflective Surface Indicating Crud 26 Deposition 9 Crud Transition Zone in Span 7 27 10 Debris in Beaver Valley Unit 1 Grids at E0C-1 28 11 Cunnulative Probability of Channel Closure in 29 Besver Valley Fuel Assembly B13 at E0C-1 12 EOC-1 Peripheral Fuel Rod Channel Closure Versus 30 Assembly Average Burnup 13 E0C-1 Axial Variation in 95th Percentile Peripheral 31 Fuel Rod Channel Closure in Beaver Valley Unit 1 14 Worst Span 95th Percentile Fuel Rod Channel Closure 32 15 Location of Fuel Assemblies Examined for Effects of 33 Coolant Cross Flow Througb Baffle Joints 16 Typical Condition of all Fuel Rods Adjacent to 34 Baffle Joints 11 1

1 FIRST CYCLE PERF0PfiANCE OF BEAVER VALLEY UNIT 1 FUEL 1.0 SCOPE OF REPORT This is a report on the evaluation of the first cycle perfomance of Beaver Valley Unit I fuel. Ninety-five fuel assemblies were exanined with binoct.lars and about thirty-five assemblies were nondestructively examined with under-water television to evaluate mechanical integrity of fuel rods and assembly grids and nozzles, crud distribution, clad corrosion, and fuel rod bow. Plant operating data, including coolant temperature, power history, assembly burnup, and coolant activity are sumarized. The crud distribution and corrosion conditions of five assemblies from each region are reported and typical conditions are documented with photographs. Peripheral fuel rod channel closures are detemined for five assemblies from each region. Closure statistics are reported for each assembly and for the three fuel re gions. The Beaver Valley rod bow behavior is compared with that of previous W 17x17 fuel. The television examination of twenty (20) fuel assemblies for possible effects of coolant cross flow through baffle joints is discussed.

2.0 INTRODUCTION

The 17x17 fuel assembly is the current design for all recent Westinghouse 3-loop and 4-loop reactors with power up to 3800 MWT and average linear power of 5. 4 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 everage kw/ft requirements imposed by the AEC Interim Acceptance Criteria. While the primary intent of the design is 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. 1

The NRC has required fuel surveillance inspections 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 assembly structural components, the fuel cladding corrosion condition, and the fuel rod bow; to compare the Beaver Valley fuel perfomance with that of other 17x17 fuel;b) and to provide data for the forecasting of perfonnance in subsequent 17x17 lel and at higher burnup. 3.0 BEAVER VALLEY UNIT 1 FUEL DESIGN Duquesne Light, Beaver Valley Unit 1 is a 3-loop 17x17 reactor with 2652 MW themal 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 first core, fuel pellet density was 95 percent of theoretical density, and the fuel rods were prepressurized with helium to (a,c) [ ]ps i g. In Table 1, several Beaver Valley Unit I core design and operating characteristics are compared with those of Salem Unit 1 (Public Service Electric & Gas Co.) and Trojan (Portland General Electric Company) reactors. While physical dimensions of the Beaver Valley Unit i fuel are the same as in the standard 17x17 design in the Salem Unit 1 and Trojan reactors, the nuclear and themal characteristics are not identical. Beaver Valley Unit 1 enrichment is slightly lower than in Salem Unit 1. Core average linear power is lower in Beaver Valley than both Trojan and Salem. (1) Beaver Valley is the sixth domestic Westinchouse desic0ed 17x17 olant to complete first cycle operation. The first fuel inspection on the Trojan fuel (Portland General Electric Co.), is reported in the public literature in Reference 1. 2

4.0 BEAVER VALLEY UNIT 1 FIRST CYCLE OPERATING HISTORY Beaver Valley Unit 1 achieved full power in the first cycle in Ncvember,1976, and it completed first cycle in November,1979, with core average burnup of 15,570 MWD /MTU (461 EFPD). The region average.burnup and power sharing at 15,570 MWD /MTU were: Cycle 1 Average Power Sharing Cycle 1 Burnup Re gion (Relative Power) (MWD /MTU) 1 I (a,c) 2 3 Reactor power history and temperature history are plotted in Figures 1 and 2 respectively. The E0C-1 burnup and power in individual assemblies are shown in Figure 3. The axial variation in power is shown in Figure 4. - The coolant chemistry was maintained with a high Li to B ratio throughout Cycle 1. Normal hydrogen overpressure control was maintained. Figure 5 shows that the coolant iodine activity remained below about 2.0 percent of the technical specification limit (i uCi/ml) for most of Cycle 1, typical of a low-defect core. 5.0 FUEL EXAMINATION At the end of Cycle 1, Duquesne Light Company and Westinghouse conducted a planned, nondestructive visual examination of five fuel assemblies from each region of the core to assess fuel assembly and fuel rod mechanical integrity, distribution of crud deposits, corrosion of fuel rod surfaces, and fuel rod bow. The assemblies examined are listed in Table 2. In addition, twenty Region 3 fuel assemblies located next to the core baffle I were examined for effects of possible coolant cross flow through baffle joints. The supplementary uamination of these assemblies was prompted by observations of local fuel assembly damage at a few leaking baffle joints in two foreign reactors. The assembifes are listed in Table 3. I l i l e --"en n + "'

5.1 Binocular Examination As fuel assemblies were transferred from the upender to the fuel storage rack in the spent fuel pool, 95 were viewed from above water at the side of the pool with 7X binoculars. Each assembly was examined as it was rotated about its longitudinal axis before it was inserted into the storage rack. The binocular examination did not reveal any anomalies such as failed rods,' damaged grids, unusual conditions of rod bow, or unusual crud distribution or corrosion on peripheral fuel rods which could require a more detailed examination with underwater television. 5.2 Television Examination five fuel assemblies from each region (Table 2) representing nearly the full range of first cycle burnup, were viewed with black and white underwater television to evaluate fuel rod, grid, and nozzle integrity, clad corrosion, crud distribution, and peripherial fuel rod channel closure. The examination was recorded on videotape for later study at NFD Engineering in Pittsburgh. Each assembly was examined at about 2X magnification to study overall physical condition and at about 10X magnification to measure peripheral fuel rod channel closure. Coincidentally, ten of the assemblies examined with television had previously been examined with binoculars. The binocular examination had not revealed any anomalies that would make the more detailed television examination necessary. 5.2.1 Iglgvjsjpg,Qagigatigg--general [ue}_Cggd!tign i The low magnification television examination was a full-surface examination of Each l all fuel assembly faces from the bottom nozzle to the top nozzle. fuel assembly was positioned in front of the television camera so that the field of view covered an area 3 inches x 4 inches of the assembly face. The assembly was lowered or raised in front of the television camera, scanning from nozzle to nozzle. The left half of the assembly face was 53 Region 1, 9 Region 2, 33 Region 3 4

examined in the first scan, and the right half of the face was examined in the second scan. Routinely, each scan was halted, briefly, at.the bottom and top nozzles and St each grid. If necessary, the scan was also stopped at any unusual surface feature for closer examination at higher magnification. Grids were examined for (a) damage such as abrasion or defomed ; traps resulting from fuel handling, (b) condition of. braze joints between edge and interior straps, and (c) condition of fuel rod spacing springs in the edge straps. The fuel assembly holddown springs on the top nozzle were examined for possible defomation which might have occurred in the reactor or during fuel handling. The criteria for evaluating fuel rod condition included (a) general integrity of clad and condition of top and bottom end plug welds, (b) reflectivity, indicating presence or absence of crud deposits, (c) crud continuity--whether the crud was intemittent, with isolatt.J local deposits or continuous, coverino significant areas of cladding surface, (d) relative thickness of crud as indicated by presence or absence of minor surface scratches that occurred during fuel rod manufacture or scratches caused by grid springs when fuel mds were loaded into the fuel assembly. No thick or unusual crud deposits or clad corrosion were observed. There was no evidence of the spalling condition typical of adversely thick crud associated with abnomal clad corrosion. Although the crud distribution differed in detail between individual fuel rods and between fuel assemblies, the crud deposits were, in general, similar for assemblies from each of the . three regions. Unifom and thin crud (estimated to be ( 0.3 mils based on reflective appearance of the surface) deposited on the bottom of the assemblies, typically up to the second grid span * (Figure 6). This was followed by a zone of

• Grid spans numbered 1-7 from bottom of assembly to top of assembly.

5

patchy crud (Figure 7), until typically the fifth gr.d span where another uniform but thicker (possibly slightly greater than 0.3 mils based on non-reflective appearance of surface) crud zone existed (Figure 8). Immediately above grid 7 near the top of the fuel column there was a crud free zone several inches long followed by a transition above the fuel column (no heat flux) back to uniform crud which then continued to the top of the fuel rod (Figure 9). There was a tendency for the Region 3 assemblies to have a wider spread of the upper uniform crud layer to the extent that on some faces the two uniform crud layers merged. During high magnification television examination (5.2.2) eight assemblies, A34, A29, A51. B31, C08, C24, C39 and C51 were found to have a small amount of debris lodged in the grids.* Figure 10 shows debris lodged under the guide tab in fuel assembly A34 at grid 6 and debris under a grid spring in grid 5 of fuel assembly B31. The debris in fuel assemblies A29, A51, C24, C39, C08 and CSI is similar to that in fuel assembly B31. Assemblies B31, C08, C24, C39 ind C51 which were returned to the core were evaluated With by f4F0 Engineering and judged acceptable for continued irradiation. the exception of the small amount of debris, all of the fuel assemblies were in satisfactory condition, fione of the fuel rods or assembly holddowt1 springs were damaged. High Magnification Televis' ion Examination--Peripheral Fuel 5.2.2 .Ro. 3..Cfi.a n.i1E.T t.T 6..s u..r s. -- ---- ~ ~ ------ ~ ~ ~ -------~ ~ -- ------ The high magnification examination consisted of transverse scans across the assembly face (a) at the end gaps between the fuel rods and the fuel assembly top and bottom nozzles, (b) imediately above and below each grid, and (c) at the mid-span position between grids. Fifteen assemblies (Table 2) were examined on each face and in each grid span.

• Assemblies C08..C24. C29 and C51 were located at baffle joints and were examined initially because of interest in possible effects of coolant cross flow through the baffle joints. (Table 3) 6

The television tapes were analyzed by NFD Engineering to detemine the peripheral fuel rod channel closures. Channel closures in fuel assembly B-13, the assembly which preliminary observations indicated had the largest number of significant channel closures, were first measured directly from the high magnification image on the television monitor using drafting dividers and a machinist's rule. Each closure in assembly B-13 was calculated from the expression: g x 100 where 1 Closure = TT + B) 2 I spacing between two adjacent fuel rods at mid-span location M = between grids spacing between two adjacent fuel rods at the top end of the T = grid span spacing between two adjacent fuel rods at the bottom end of B the grid span Thus, the individual channel closures of fuel assembly B-13 are detemined relative to the average measured spacing for the top and bottom ends of the channel. The cumulative freasency distribution of closures in assembiv B-13 are sumarized in Table 4 and in Fioure 11. From the cumulative frequency plot it is noted that the 95th percentile closure for all spans is[ ] (a,c) In order to expedite the detemination of channel closure statistics for all 15 fuel assemblies an alternate, simpli,fied procedure was adopted i following verification of its validity by comparison with the detailed divider measurements on fuel assembly B-13. In this procedure the 896 divider measurements of channel spacing at the grids of assembly B-13 were first averaged to detemine a single mean value for the spacing at all grids. lie lo variability in the distribution of divider measurements at the grids wasabout[' ]assumin'g th'e nominal preirradiation channel spacing (a,c) of 122 mils. i 7

I Assuming that the above calculated nominal post-irradiation spacing at the i grids is not significantly different from the nominal pre-f rradiation spacing, a measuring gauge was constructed with graduations corresponding to[ (a,c) ] channel closures. The gauge was then used to measure mid-span channel closures from the high magnification television image. Closures less than [ ]were not recorded. Closures [ ]were (a,c) assigned to the two closure intervals [ ] There was no (a,c ) effort to measure or estimate individual closures more accurately within either of the two intervals. Closures equal to or greater than[ ]were (a,c) measured and recorded individually using the dividers and machinist's scale as described above. From time to time channel spacings at the grids were measured with dividers and machinist's scale to verify that the initial measurements on assembly B-13 and the calculated r.ominal spacing at the grids, which were the basis for the measuring gauge, remained valid for the assembly being measured. In Figure 11, the cumulative frequency distribution of channel closure as obtained by this technique *, is illustrated for fuel assembly B13. The closure distributions in the 15 assemblies are summarized in Table 4 Only[ ]of the 6720 peripheral channels were closed [ 3and the (b,c) maximum closure was[ ] The 95th percentile closures were detemined (b,c) graphically on cumulative probability graph paper for each of the 15 assemblies as illustrated in Figure 11 The 95th percentile closure for individual assemblies increases with increasing burnup (Figure 12) consistent with previous W experience. The axial distribution of channel closure, shown in Figure 13, is similar to that observed in the Trojan fuel at comparable burnup, U )[ ] The Span 1 closure in ( b,c) Figure 13 has been nonnalized to compensate for the longer length of the

• Numbers of closures in each gauge interval are added to deduce the cumulative number of closures below[

] channel closures respectively. (a,c) I 8 i J

first span (24 ~ inches in Span 1 and 20 inches in the upper spans)* and, therefore, the greater tendency to bow in Span 1 than in the upper spans. It is seen in Figure 13 that the Region 1 and 3 closures are closely comparable and that the largest difference between the three regions was [ 3 closure (Span 2). (b.c) The worst span region-wise 95th percentile closure is the significar.t statistic for licensing purposes. In Figure 14 the Beaver Valley worst span closures are compared with those in the Surry demonstration 17x17 assemblies, in Trojan at ~ EOC-1, and in Salem at about the same first cycle burnups. The Surry data (7 grids) have been nomalized to the same scan length as the 8-grid standard 17x17 fuel in the other three reactors. The burnup dependence of Beaver Valley closure parallel that in the other reactors and is well below the NRC rod bow design curve. 5.2.3 Exagigatigng{,@glassggbligs,at,Bafflg,ygigts Recent fuel inspections at two foreign reactors revealed that coolant cross flow through leaking baffle joints impinged against peripheral fuel rods causing fuel rod vibration and fuel rod fretting wear in the grids and against the baffles. Since the Beaver Valley, ad the two foreign reactors have similar baffle l l joint geometries, assemblies in Beaver Valley adjacert to these joint types were examined. Twenty fuel assemblies (Table 3 and Figure 15) were inspected to determine the condition of the fuel rods and of the corresponding grid l cells located adjacent to the baffle joints. No features characteristic l of baffle leakage and severe fuel rod vibration (wear or perforation of clad caused by rod vibration against the baffle, damaged grid springs, or rods mispositioned in the grids as the result of fretting at grid springs or dimples) were observed on any of the fuel rods or grids. Examples, illustrating the l condition of these fuel assemblies, are provided in Figure 16. l The conclusion is that no large amplitude fuel rod vibration occurred on the peripheral rods adjacent to the baffle joints.

• Span 1closureisnormalizedbymultiplyingbytheratio(h).

9

6.0

SUMMARY

The visual examination of a representative sample of Beaver Valley Unit 1 fuel assemblies after one cycle of operation showed the assemblies to be in excellent condition. Crud deposits were negligible; there was no evidence of thick crud of the type which would cause concern about excessive corrosion. With the exception of a small quantity of debris in a few assemblies--which was judged to have no impact on fuel performance--no anomalous condition was observed. (b.c) Less than[ ] percent peripheral fuel rod channels in 15 assemblies were closed [ ] The 95th percentile worst span rod bow is well (a,c) within the NRC design limit and comparable to that observed in other W 17x17 fuel.

7.0 REFERENCES

!!elehan, J.B., DeStef ano, J., Bal four, it. G., and Cerni, S., Evaluation 1. and Performance of Westinghouse 17xl7 Fuel, ANS Topical t!eeting on Light Water Reactor fuel Performance, Portland, Oregon, April 30-May 2, 1979. 10

TABLE 1 CORE DESIGN AND OPERATING CHARACTERISTICS f Beaver Valley Salem Unit 1 Unit 1 Trnien U0 Enrichment w/o U-235 2 Region 1 2.10 2.25 2.10 Region 2 2.60 2.80 2.60 Region 3 3.10 3.30 3.10 i Coolant Temperature Hot Zero Power, UF 547.0 547.0 557.0 Initial Inlet 542.5 538.2 552.5 i Initial Core Ave. HFP, OF 577.7 571.5 585.1 Operating Coolant Pressure, psig 2250 2250 2250 Average Linear Power kw/ft 5.2 5.33 5.44 11

TABLE 2 SCOPE OF BEAVER VALLEY UNIT 1 EOC-1 PLANNED FUEL EXAMINATION Assembly Average Fuel Core Burnup Examination Television (a) Assembly Location (MWD /f1TV) Binocular A29 D-10 17210 X X A34 B-8 14990 X X A29 G-9 18090 X X A50 N-7 16760 X X A51 D-4 13760 X X B4 E-10 18350 X B7 M-5 16450 X l B13 J-12 18170 X B20 N-10 16100 X X 831 C-6 18720 X C3 B-10 13270 X x C6 B-7 15100 X X C15 L-3 14910 X 11180 v. X C39 R-8 C49 A-9 8910 X (a) Each assembly was examined at both high and low magnification. I f l i 12 l ~ , _. ~.

TABLE 3 BEAVEP VALLEY #1 E0C-1 FUEL EXAMINATION, ASSEMBLIES ADJACENT TO CENTER INJECTION BAFFLE JOINTS Assgggly,jg 9 99 C-03 1 l C-07 4 C-23 4 l C-38 4 C-51 4 I C-17 1 C-24 1 C-11 1 C-10 1 C-19 2 C-03 2 C-29 2 C-37 2 C-42 2 C-21 3 C-45 3 C-20 3 C-30 3 C-13 3 C-36 4 J 13

n.,.

a - -

/ TABLE 4 EOC-1 PERIPHERAL FUEL R00 CHANNEL CLOSURES IN BEAVER VALLEY UNIT 1 FUEL ASSEMCLY B-13 i Number of Channels with Indicated Closure * (b,c) Face Span 1 1 I 2 3 4 5 6 7 2 1 ? 3 4 5 6 7 3 1 2 3 4 5 6 7 4 1 2 3 4 5 6 7 All others

• Number in parentheses indicates closures measured with gauge.

measured with dividers and machinists scale.

• • All closures, other than those identified, were less than[

jof nominal channel (b,c) spacing. 14

TAht:. 5 E0C-1 PERIPilERAL FUEL ROD CHANNEL CLOSURES IN BEAVER VALLEY UNIT 1 FUEL ASSEMBLIES Fuel Assembly . Span (b.c) A29 7 6 5 4 i 3 2 1 4 A34 7 6 5 4 3 2 1 A39 7 6 5 4 3 2 I 1 A50 7 6 5 4 3 2 1 15

TABLE 5 (CONTINUED) Fuel Assembly Span (,,, A51 7 6 5 t 4 4 3 2 1 B04 7 6 5 4 3 2 l 1 1 B07 7 i 6 i 5 4 3 2 1 B20 7 6 5 4 3 2 1 16 l l l

1 TABLE 5 (CONTINUED) Fuel Assembly Span (b.c) B31 7 6 5 { 4 3 l 1 B13 7 i 6 { 5 I 4 i j 3 1 2 1 C03 7 6 1 j 5 4 4 l 2 ] C06 7 1 6 l i 4 I 3 i 2 I t 9 9 I 17 i i l

TABLE 5 (CONTINUED) Fuel (b.c) Assembly Span C15 7 6 5 4 3 2 1 C39 7 6 5 4 3 2 1 C49 7 6 5 4 3 2 1 \\ 18

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13 784-2 600 590 c' w 580 L i D I ~' Q 570 j g 560 g I L 550 w c< $ 540 E 530 2 5 520 8U 510 500 0 100 200 300 400 500 600 700 800 900 1000 1100 TIME (DAYS SINCE FIRST DATA POINT) Figure 2. Coolant Average Temperature History 20 l

l 16793 3 R P N M L M J H G F E D C B A 1 2 3 l 4 5 6 7 i t 8 90e 270' 9 10 11 12 13 14 15 = REGION xxx EOC 1 ASSEMBLY AVERAGE RELATIVE POWER xxxxx EOC 1 ASSEMBLY AVERAGE BURNUP, MWD'MTU Figure 3. EOC 1 Power and Burnup of Beaver Valley Unit 1 Fuel Assemblies 21

16784-1.2 fu,.s+. , = > 14 .<g. 0.8 e y e $_ 0.6 E 0.4 g-NOTE: POWER IS RELATIVE TO CORE AVERAGE POWER OF 1.00 0.2 CORE CORE BOTTOM TOP 0 144 120 96 72 48 24 0 AXIAL LOCATION, INCHES Figure 4. Time-Averaged, Radial-Averaged Power Profile 22

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k 1 S O A g A ) #,e e A A9 9 97 /6 1 elcy C 3 1 g D: 3 3 n 1 1 i r N i1 u E D G A$ 87 t E / n L 2 lo a 1 o C 1 i:n U A 9 y le laV 87 r / e 6 v Ae ae B n A e i y A s itv A e i tcA A 9 e 7 n 7 i / d 2 o A e 1 l 5 e ru A 9 ig F sA e 7 A G 7 /6 e-1 2 3 4 5 0 0 0 0 0 1 1 1 1 1 Edy $58o z >bbv yg9 l!lll

WESTINGHOUSE PROPRIETARY CLASS 2 17446-3 i (, 4 l !i TYPICAL REFLECTIVE APPEARANCE OF FUEL RODS IN SPAN 2 OF FUEL ASSEMBLY B04 d[ i i Figure 6 Reflective Surface of Rods in Bottom Spans ~

WESTINGHOUSE PROPRIETARY CLASS 2 17446-2 i 7;- y i 3 ~ .1 , y: PATCHY CRUD SHOWN AT LOW MAGNIFICATION IN SPAN d OF FUEL ASSEMBLY B04 wq s. F 9' 4 %. l. PATCHY CRUD SHOWN AT HIGH MAGNIFICATION IN SPAN 3 OF FUEL ASSEMBLY B31 Figure 7 Typical Patchy Crud in Spans 3 and 4

WESTINGHOUSE PROPRIETARY CLASS 2 17446-4 I J j TYPICAL NON-REFLECTIVE SURFACE OF FUEL RODS IN SPAN 5 OF FUEL ASSEMBLY A34 4i i Figure 8 Typical Non Reflective Surface :.7dicating Crud Deposition .b =

r l YlESTINGHOUSE PROPRIETARY CLASS 2 17446 6 l ?; S, ( e l 3'.,

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(.- ~ ~ ^i. INCREASED CRUD P OF L COLUMN p DECREASED CRUD .- ( .t. ) ~' 2 . s .2 2. TRANSITION FROM ZONE OF LOW CRUD DEPOSIT TO ONE OF HIGHER DEPOSIT IN SPAN 7 DIRECTLY ABOVE THE AREA SHOWN IN PHOTO BELOW 3... f ..l ' 5 r ~ p r i. A .e, ( TRANSITION FROM CRUD ZONE TO ZONE OF LESS CRUD ABOVE GRID 7 F/A A39 Figure 9 Crud Transition Zone in Span 7 om m g-J o o Ju o JL . A ini.m

WESTINGHOUSE PROPRIETARY CLASS 2 17446-5 i i i 1 1 'p q Aa ',:._4

=

AA.,. "J. 1., 't< ' ' >. DEBRIS ATTACHED TO TAB OF GRID 6, t FUEL ASSEMBLY A34 n'~ -3: .? .~ ,n 2 i Q~, ^ x"O

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'r;g;Ep. 7 + -- ~ ; yl,l-; w +' w g; DEBRIS LODGED IN GRID SPRING SLOT OF GRID 5, FUEL ASSEMBLY B31 Figure 10 Debris in Beaver Valley Unit 1 Grids at EOC 1 i dc _:s

16.784 6 (a,b,c) 0 0.05 0.1 0.2 0.5 1 2 5 I 10 5o $ 20 z_ > 30 2 40 m j 50 8 s0 n. w 70 2 y 80 a 3 lEo 90 u 95 98 99 99.8 99.9 I 99.99'

• 30 10 0 10 20 30 40 50

~* OPENINGS CLOSUhES CHANNEL CLOSURES (PERCENT) l Figure 11. Cumulative Probability of Channel Closure in Beaver Valley Fuel Assembly B13 at EOC-1 29

l 16.784 7 l 35 b.b.c) 30 D 2 y 25 m E w C bg 20 0 a w 2 2< I u 15 Zw U Zw' 10 I $e 5 0 0 5 10 15 20 IS FUEL ASSEMBLY AVERAGE BURNdP (MWD /MTU X 10-3) Figure 12. EOC-1 F.. ';heral Fuel Rod Channel Closure versus Assembly Average Burnup 30

16784 8 40 ~ (a,b.c I 30 2 Uz E we 3 O .Ju J w 2 20 24Io w =fnz Ue E I H$ 10 0y 0 1 2 3 4 5 6 7 8 GRID SPAN I Figure 13. EOC-1 Axial Variation in 95th Percentile Peripheral Fuel Rod Channel Closure in Beaver Vat!ey Unit 1 31

100 LEGEND: 6 SURRY 1 & 2 MEASURED DATA, 7-GRIDS A SURRY 1 & 2 NORMALIZED TO 8-GRID SPAN LENGTH h 9 TROJAN 1 CYCLE, 8-GRIDS

• 80 X BEAVER VALLEY UNIT 1 1 CYCLE, 8-GRIDS

{ E NOTE: ALL DATA POINTS ARE FOR w COLD CONDITIONS NRC NEW DESIGN VALUE 3" 60 17 X 17 HOT 8-GRID o .J NRC NEW DESIGN VALUE y ~7 X 17 COLD 8-GRID k SURRY U 4:0 'OUNIT '2 "j SURRY g 1 CYCLE o X R2 2 UNIT 1 R1X UNIT 20 R3X 'r A 20 ,r'r g E 0 0 5000 10000 15000 20000 25000 30000 35000 BURNUP MWD /MTU E a Figure 14. Worst Span 95th Percentile Fuel Rod Channel Closure ~

l l 16 784 to l l R P N M L x J H G F E D C B A 180 '--,f 94 l l 2 tC13 C36 t t C7 hC30 hC5 3 f C20 fC5 4 I 5 t i* 9 CSI 6 C45 C17 9 y '.+ NOT E : ARROW INDICATES DIRECTION OF COOL ANT CROSS Flow 8 90 IN EVENT OF BAFFLE JO6NT LEAKAGE 270 9 /-* t +~ L 4 to C21 C3 11 C42 i I 12 C37 C34 13 .._t C1T Czs i 14 C8 A I iC19 C10 'S +f + F ACE 4 0 FACE 3 FACE 1 F ACE 2 Figure 15. Location of Fuel Assemblies Examined for Effects of Coolant Cross Flow Through Baffle Joints 33

WESTINGHOUSE PROPRIETARY CLASS 2 17446-1 ) .-. ;.. - - ~,;, g.. - \\l l. ~ k.,

h',

p Q y 'i. J s MID SPAN OF FUEL RODS IN FUEL ASSEMBLY C07 = ' + w BOTTOM OF GRID 4 OF FUEL ASSEMBLY C17 FACE 1 Figure 16 Typical Condition of Fuel Rods Adjacent to Baffle Joints i -}}