ML19289E246

Summary of 790130 Meeting W/B&W in Bethesda,Md,Re High Burnup Programs.W/Supporting Documentation

ML19289E246
Person / Time
Issue date:	03/20/1979
From:	Houston D Office of Nuclear Reactor Regulation
To:	Kniel K Office of Nuclear Reactor Regulation
References
REF-SSINS-0600 NUDOCS 7904070046
Download: ML19289E246 (28)

Text

/

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i i

8 UNITED S CATES b

,k NUCLEAR REGULATO7Y COMMisslON Y I 1 S

WASHINGTON a C. 20555 Wu/ I%l,' f]

THIS DOCUMENT CONT s

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POOR QUAUTY PAGES MEMORANDUM FOR:

K. Kniel, Chief, Core Performance Branch, OSS 7,

THRU:

R. Meyer, Leader, Reactor Fuels Section, CPB, DSS, FROM:

D. Houston, Reactor Fuels Section, CPB, DSS

SUBJECT:

MEETING

SUMMARY

BABC0CK AND WILC0X HIGH BURNUP PROGRAMS 30, 1979, a meeting was held in Bethesda with represen-On January tatives from Babcock and Wilcox (B&W), Arkansas Power and Light, DOE and NRC to discuss the current B&W programs for extended fuel These programs involve both lead test assemblies and burnup.

fuel reload batches and have an average assembly burnup goal in the range of 45,000 mwd /tV. A copy of the B&W vugraphs and an attendance list are attached.

Extended life or high burnup programs for B&W Mark B (15x15) fuel are currently underway at Oconee Unit 1 and are planned for Arkansas Nuclear One Unit 1.

These programs are funded by DOE as part of a study to improve the operating performance of LWRs and increase the utilization of uranium.

In Oconee 1, five fuel assemblies of normal B&W design are being operated fcr one additional cycle and will achieve an end-of-cycle burnup in the range from 38,000 to 41,000 mwd /tU.

These assemblies will be discharged in June 1979 and are scheduled for extensive post-irradiation examination.

Lead test assemblies (LTA) designed for high burnup will be irradiated in ANO-1.

LTAs of a conservative design are scheduled for insertion late in 1980. LTAs with an optimum design are scheduled for The first reload batch of high burnup design is early 1982.

proposed for 1988 and is planned to achieve an average assembly burnup of 45,000 mwd /tU.

An operational limit report for Mark B cores at higher burnup is being prepared by B&W and is scheduled to be finished in 1980.

In this report, topics relating to mechanical early design, thermal-hydraulic design, ECCS, safety and control will be discussed. The report will include a SAR, Chapter 15 review and present doses for related accidents.

790407004Q

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s MAR c 31:

K. Kniel Increased uranium utilization is one of the goals of this program.

B&W is performing studies in the following areas to achieve this goal: optimum burnup, axial power shaping rod removal, moderator temperature control, reduction of uranium in fuel rods and extended burnup of batch 1 and 2 fuel. These studies are scheduled for completion by the end of 1979.

Next, B&W discussed a parametric study of design variables.

The objective was to determine the effect of beginning-of-life parameters, for example, cladding thickness, pellet density and gap size, on end-of-life parameters such as, bowing, collapse, and swelling.

The results of these studies will be applied for design of the optimized LTAs for ANO-1.

An extensive fuel examination program was discussed as it relates to the selection of fuel for higher exposure in Oconee 1 and to obtaining design data for and from the LTAs.

Both non-destructive and destructive tests will be used.

Details of these tests can be found in the vugraphs.

The last page of the enclosure is taken from a submittal of a previous meeting with B&W on May 2,1978 when the Cconee 1 demonstration program was discussed with DOR.

It is included here to provide a better description of the confirmatory data to be obtained from the Oconee i fuel.

NRC asked about the status of the Environmental Impact Statement for this program.

DOE, indicated that it may be submitted for comment in approximately two months.

At the conclusion of the meeting, B&W requested that NRC review the technical details as presented in the meeting and the vugraphs.

Specifically, B&W wants NRC to determine if the post irradiation examination program is adequate to cover all licensing concerns for high burnup fuel.

If any concerns are identified, please submit them to Dean Houston, ext. 27603 by May 1,1979.

>>7 z ' 'e, Anw.k%~

M. Dean Houston Reactor Fuels Section Core Performance Branch Division of Systems Safety

Enclosure:

As stated

G'; c a :379 i

K. Kniel ;

Distribution:

Meeting Attendees i

CPB Members P. Check J. Collins D. Nellis C. Haupt R. Hartfield Z. Rosztoczy W. Butler T. Novak W. Johnston R. Tedesco NRR ads R. Fraley, ACRS (16)

R. Mattson/F. Schroeder NRC PDR R. Lobel S. deiss C. Berlinger i

B&W High Burnup Programs January 30, 1979 Meeting Attendees NRC K. Kniel, DSS /CPB H. Richings, DSS /CPB D. Houston, DSS /CPB M. Tokar, DSS /CPB E. Adensam, DOR /EEB F. Coffman, 00R/RSB J. Rosenthal, DOR /RSB S. Diab, DOR /RSB F. Cardile, DSE/ETSB R. Cleveland, DSE/EP-1 J. Meyer, DPM/ARB P. Boehnert, ACRS R. Barker, SD/TPSB DOE P. Lang, NPD B&W R. Trost T. Coleman R. DeMars J. Willse D. Nitti R. Borsum AP&L

0. Cypret T. Enos

EXtelMlCd bH771Up [.Y0fEr0U

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v Progm.1 JOE / Juke 0v!er Co./ 3&W 3

Objs.ctive

(!ualification of Mk-B for high burnup target 40,000 mwd /t assem aly l

2 roc: am 2 JOE / Arkansas Power & Light /B&W l

P '.. r a1 Develop extended burnup design for Gbjective Mk-3 target 50,000 mwd /t assembly F aase 2

.rradiation of "Leac " assemlies o

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I High burnup characterization of Mark B fourth cycle irrac'intion in Oconee 1 Design & licensing cyclo 5 l

irradiation Poolside Poolside Hot ce;! ex:in i

Oconee 1 Cycle 4 Cycle 5 Cycle 6 Cycle 7 u

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l 1978 1979 1980

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1. "Optininin " burnup Daturniine "opiiroun1" buruup s tu dis.s b:

.d on today's fuul cycle econornics

2. APSR removal E

.mine contro! leclunque f or renioval

3. Maderator teinperature E:.tiroate potential U :.0,, savmgs a

o Culi!! ol

.l. l' eduction of uranium in Estirnate potential U 0 3 savings 3

fuel pins 4

5. Extended burnup of Estimate potential U 03 8 savings batches 1 and 2 k

k CD O

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Moderator temperature control

.g k nd of full power increased E

N.

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savings i

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Fuel utilization studies Optimum burnup determination l.iliteset pr ep.ir ation I

Inel ayale. A 1

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Economic analyses & report preparatson

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l APSR removal' lAI Ml.1 !.1 : Al SI01N1 D JtI iMlA t Mi ii 11 A1 S t_ O I Nl l

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1 P0iranei. sic Sind503 Of design VariBED.:.;

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C E d 3 g fi 0!!iaTf U p S i

EOL p. rc.inctors BOL paramotors a

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Cladding thickness Pin pressure Deg'ree of cold work Fhel temperatures' Determine effects Pre-pressurization level C~reop collapse

?

of

<' Fuel density

. Stress and strain levels Pellet dimensions On< Fatigue Gap size Pellet. swelling a

Plenum volume Enrich men t Grid grip Rod bow.

~

Ovalit~y Fretting

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Hold down springs Identify key design constraints on extended burnup assembly design j

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i Parametric studies t

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IULL ROD DE SIGN i

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BASIC SIRUCIURAL COMPONENT DLSIGN i

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l DESIGN ANALYSIS INIERf ACES I

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CONSERVATIVE OPllMlZED LTA DESIGN LI A DESIGN A

A 1978 1979 1980 1981 i

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IMPLEMENTATI0t1 EVALUATIOr4

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o Gross gamma scans 5 Assernbly ength and gric ocations o Water channe' measurements L_ine scan pro'iiometry O

o HOLdc.own spring Load-def ection characteristics o Surface deposit claraclerizaiion i

o Spacer gric.

oac,-def ection characteristics p

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• p

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cJ Cconeei End of cycle 3 DOE examinations SCOPE

. EX Atal fl AI 10tl ALL 5 ASSEMBLIES e

VISUAL EXAM ALL 11 CORtlER RODS - ALL 5 A,SSEMBLIES e

GROSS GAMMA SCAtlS ASSET 4BLY LEtlGTilS AtlD GRID 10 ASSElyou.ES - ALL 14 FACES e

LOCAfl0tlS ALL 5 ASSET 4BLIES 4

110LDDOWil SPRillG FULL SCAtl 11 ASSEMBLIES

~ 10,000 ROD TO WATER Cil AtitlEL MEASUREMEllTS ROD SP ACitlGS t

PARTIAL SCAN I ASSEf4BLY 2,000 ROD TO

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4 DI At4ETER PROFILOMETRY i

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dO9trMCt!VO iGGt phaSO t Roc lengtils; pul.ing forces O C ad profi ometry, thickness ~-

o C ac' de"ect scans, gamrna-scans o Surriup, Jission gas ana ysis

. o CrucL sann ing anc. ana ys'is o Pe,et density

~

o C,ad meclanica' projierties o [i!!etal ography e

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equilibrium xenon, group 8 insertea I

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o 1.028 1.093

.947

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MWD / MTu 1.091

.933 1.148

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28479 37208 H8 H11.M 8 31135 40395 i

R

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-l OPTInun BuRMUP FUEL CYCLES FEED CORE EOUILIBRIUn FOUILIBRIUM MODE OF E0uiLieRiun Ef1RICHMENT BATCH F0WER CYCLE LENGTH BATCH BURNUP_

SIZE LEVEL (Mk0 OPERATION 460

~3f:,000

~3.5 30 2772 FEED E BLEED 116 0 st10,000 s3.8 60 2772 FEED & BLEED st!.1 1160 sil6.,000 60 2772 FEED & DLEED fi97

~46,000 sfl.1 60 2563 RoooED

~4.0 292

~43,000 36 2772 FEED & BLEED LGB E9

ac 55o m

(D C

Q c_m O

-1 FEED ENRICHMENTS (% U-235)

FEED BATCli CORE POWER IiODE OF CYCLE CYCLE CYCLE CYCLE SIZE LEVEL (Illl)

OPERATION tl + 1 ll + 2 Il + 3 N + 11 80 2772 FEED & 3LEED 3.220 3.l!80 3.539 3.376 68 2772 FEED & BLEED 3.803 3.803 3.303 3.803 60 2772 FEED 3 BLEED 11.106 11.106 ti.106 11.106 36 2772 FEED & BLEED (1.020 11.020 4.020 4.020 60 2568 RODDED 4.106 4.106 11.106 11.106 O

!9 tuis IS

t.

Q CYCLE LIFETIMES (EFPD) c IT1 Q

DESIRED EQUILIBRIUM MODE OF CYCLE CYCLE CYCLE CYCLE FEED CORE BATCH POWER N+1 fl + 2

!! + 3 N+4 CYCLE LENGTH OPERATION-LEVEL (f20_

SIZE 80 2772 FEED & BLEED 396 450 4E2 460 l!E0 IIE0 E3 2772 FEED & BLEED 4tl7 453 60 2772 FEED & ELEED 430 427 487 459 110 0 292 36 2772 FEED & BLEED 469 467 520 119 8 497 60 2568 RODDED tAl I3 9

s g

?

5i

~m O

-1 POWER PEAKING ERCENT MRGIN TO DESIGN LIMIT E INIMUM MODE OF CYCLE CYCLE CYCLE CYCLE FEED CORE

!!+1 N+2

!!+3 N+4 BATCH POWER Size LEVEL OPERATION 15.5(150) 15.5(B0C) 11.7(E0C) 3.4(FOC) 00 2772 FEED 8 PsLEED 7.0(B0C) 60 2772 FEED & CLEED 5.1(B0C) 6.2(150) 8.5(B0C)

I!.5(30C) 60 2772 FEED & OLEED 36 2772 FEED E BLEED 0.8(B0C) 0.11(420) li.4(B0C)

11. 5 (I163 )

60 2563

' RonDeD tat I3 9

/

r 8

2 R

i.

(D C

(D c_m O

-l DISCHARGE BURNUPS FzEo 3ATCH CORE P0weR MODE OF CYCLE CYCLE CYCLE CYCLE FOUILIBRIUM SIZE LEVEL (MlD OPERATION N+1 N+2 h+3 N+11 CYCLE 80 2772 FEED & DLEED DISCH. AVE.

27391 31739 33027 34770 34382 MAX. ASSY.

33531 3 5118 3 37705 39552 MAX./ AVE.

1.23 1.12 1.14 1.14 68 2772 FEED & BLEED DISCH. Ave.

32033 thx. ASSY.

375711 thx./ AVE.

1.17 60 2772 FEED & DLEED DISCH. AVE.

3 2117 8 39477 115097 45891 45838 MAX. ASSY.

112224 115979 52 5112 54506 MAX./ AVE.

1.30 1.16 1.17 1.19 36 2772 FEED & BLEED DISCH. AVE.

MAX. ASSY.

Dd IEl 60 25E8 RODDED DISCH. AVE.

325'19 3921:3 45162 115673 115838 MAX. ASSY.

42858 47125 54320 55713

g max./ AVE.

l'.32 1.20 1.20 1.22 2g is 8o

./

I 177 ASSET'3LY CORE i

LBP SHUFFLE SCHEEE 60-FEED 18 t'ONTH CYCLE WEIGHT PERCENT BqC IN LEP Roo:

8 9

?O 11 12 13

/

1a 15 i

/

j l

1. 5 '

1.5 i 1.5 H

l K

1.5 1.5 1.5 1.5 l

I t

l i

1.5 i

1.5 L

I a

1.5 1.5 i

1.5 i

1.5 1.5 n

i t'

i o

1.5 l

\\

1.5 a

LEGEND 60 FRESH ASSE.BLIES M

g WITH LEP CLUSTERS EO ONCE BUFRED ASSET'3 LIES NO LBP t

57 TUICE BUPf!ED.5.SSE"BLIES NO LBP E CATALOG NO.15 41 1 A. lF CT 3M CENTER, ST. P4

. ~ -

177 ASSEMBLY CORE LBP SHUFFLE SCHEME 80_ FEED 18 MONTH CYCLE WEIGHT PERCENT 8 C 4

IN LBP RODS 8

9 10 11 12 13 14 15 y

r i

)

i H

1.8 1.8 1.6 A

)

i i

i

,y K

1.8 1.8 1.6 1.4 i

s N

L 1.8 1.8 1.4 N,

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1.8 1.8 1.4

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1.6 1.4

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LEGEND 8

FRESH ASSEMBLIES

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P 1.4 O

WITH LBP CLUSTERS 80 ONCE-SURN ED ASSYS NO LSP R

17 T# ICE-80RNED ASSYS NO LBP i

I

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+.,

J nlFF'W;dP*. n -, x -

TABLE 1 5f g HOT CELL EXAMINATI0f1 0F EXTEf1DED BURNUP FUEL h

,5 A.

BUNDLE 1.

TV examination of fuel assembly for shipping damage

.h s

B.

INTACT RODS (16 Selected Rods) h 1.

Removal of individual rods from the assembly and measurement of 1

h extraction loads.

'I 2.

Visual examination of each rod.

3.

Gross and isotopic gamma scanning (each rod).

1 4.

Full profilometry scans (each rod).

5.

Eddy current scans for clad defects -(each rod).

6.

Rod length measurements (each rod).

7.

Internal rod pressure and void volume measurements (each rod).

i 8.

Fission gas analysis (each rod).

J 9.

Crud chemical analysis of 2 samples from each of 4 rods.

1 C.

SECTIONED RODS (8 Selected Rods) 1.

Metallographic examination of cladding and fuel - 3 sections / rod l

(total 24).

2.

Tensile tests of clad sections at 650*F - 2 specimens / rod (total 16).

j 3.

Hydrogen analysis of cladding - 8 specimens total.

4.

Chemical burnup analysis - 12 samples.

5.

Fuel density determinations - 3 specimens / rod.

6.

Cladding burst tests at 650*F - 8 specimens total.

7.

Optical examination of crud layer.

8.

Waste materials will be disposed of in the normal manner.

-