June 14 2000 MEMORANDUM TO: Stuart A. Richards, Director

Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

FROM: Stewart N. Bailey, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

/RA/

SUMMARY OF THE JUNE 1, 2000, MEETING WITH FRAMATOME ON INCREASING THE BURNUP LIMIT ON MARK-BW FUEL ASSEMBLIES

On June 1, 2000, the U.S. Nuclear Regulatory Commission (NRC) staff met with Framatome Cogema Fuels, Inc. (FCF), to discuss a future submittal to increase the burnup limit on Mark-BW fuel assemblies to 62 GWD/MTU. FCF's Mark-B fuel is currently licensed to 62 GWD/MTU, but the Mark-BW fuel, which seems slightly higher in temperatures, is limited to 60 GWD/MTU. The submittal would include a revision of Topical Report BAW-1 0186, "Extended Burnup Evaluation," and a clarification of Topical Report BAW-1 0227, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Fuel."

FCF and the staff discussed (1) the fuel performance data that FCF has taken since the last revision of BAW-1 0186, which set the current burnup limits, (2) the comparison between the performance of Zircalloy 4 cladding and M5 cladding, and (3) other design considerations of increasing the burnup limit. The staff asked FCF, in its submittal, to clarify the effects of using M5 cladding and/or M5 structural material. The staff also noted that the majority of the data for the Mark-BW fuel was limited to approximately 53 GWD/MTU, so that increasing the Mark-BW burnup limit to 62 GWD/MTU would rely on an extrapolation of the available data and on the similarity of the Mark-BW fuel to the Mark B fuel, which has data at higher burnup levels.

A list of those attending the meeting is provided as Attachment 1. The non-proprietary slides used by FCF during the meeting are provided as Attachment 2.

Project No. 693

Attachments: 1. List of Meeting Attendees 2. FCF's Non-Proprietary Slides

cc w/atts: See next page DISTRIBUTION: E-Mail J. Zwolinski (RidsNrrDlpm) S. Black (RidsNrrDIpm) S. Richards (RidsNrrDlpmLpdiv) A. Mendiola (RidsNrrDIpmLpdiii-2) S. Dembek (SXD) RidsNrrLAEPeyton RidsNrrPMSBailey RidsOgcMailCenter RidsAcrsAcnwMailCenter R. Caruso M. Chatterton S. Wu K. Landis Accession No. ML00371

OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC

NAME SBailey:lc E' y SDembe

DATE 4//_ _ 4 00 i// -/O 1

DOCUMENT NAME: G:\PDIV-2\B&Wog\MTS000601.WPD OFFICIAL RECORD COPY

Hard Copy PUBLIC PD IV-2 r/f

B&W Owners Group

cc:

Mr. Guy G. Campbell, Chairman B&WOG Executive Committee Vice President - Nuclear FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Rt. 2 Oak Harbor, OH 43449

Ms. Sherry L. Bernhoft, Chairman B&WOG Steering Committee Florida Power Corporation Crystal River Energy Complex 15760 West Power Line St. Crystal River, FL 34428-6708

Mr. J. J. Kelly, Manager B&W Owners Group Services Framatome Technologies, Inc. P.O. Box 10935 Lynchburg, VA 24506-0935

Mr. F. McPhatter, Manager Framatome Cogema Fuels 3315 Old Forest Road P.O. Box 10935 Lynchburg, VA 24506-0935

Mr. R. Schomaker, Manager Framatome Cogema Fuels 3315 Old Forest Road P.O. Box 10935 Lynchburg, VA 24506-0935

Mr. Michael Schoppman Licensing Manager Framatome Technologies, Inc. 1700 Rockville Pike, Suite 525 Rockville, MD 20852-1631

Project No. 693

FRAMATOME COGEMA FUELS, INC. MEETING ON INCREASING MARK-BW FUEL BURNUP LIMIT

JUNE 1. 2000

AFFILIATIONNAME

Stewart Bailey Ralph Caruso Muffet Chatterton Shih-Liang Wu Garry Garner Frank McPhatter Rick Williamson John Willse Millan Straka Ian Rickard

NRC/NRR/DLPM NRC/NRR/DSSA/SRXB NRC/NRR/DSSAISRXB NRC/NRR/DSSA/SRXB FCF FCF FCF FCF NUSIS Westinghouse

Attachment 1

NRC/FCF Meeting on Mark-BW Burnup Limit

Rockville, Maryland

C. F. McPhatter

June 1, 2000

cfm6_OOnrc.ppt

Agenda

"Introduction and Background for Increasing Mark BW Burnup Limit

" Presentation of Data

"Discussion

"UConclusion

cfm6_OOnrc.ppt

I Objectives

EAgree that the proposed burnup limit for the Mark-BW fuel is justified

U Develop plan for providing documentation and obtaining NRC approval

cfm6.OOnrc.ppt

I Reference Documents

*BAW-10153P, Extended Burnup Evaluation, April 1986

* BAW-10172P, Mark-BW Mechanical Design Report, SER, December 1989

*BAW-10186P-A, Rev. 1 Extended Burnup Evaluation, April 2000

* BAW-1 0227P-A, Evaluation of Advanced Cladding and Structural Material (M5TM) in PWR Reactor Fuel, February 2000

cfm6_OOnrc.ppt

I Background

lThe SER for BAW-10153P-A allows burnups up to 45 GWd/mtU batch average for Mark-B fuel

nThe SER for BAW-1 01 72P allows burnups up to 60 GWd/mtU rod average for Mark-BW fuel

"EThe SER for BAW-10186P allows burnups of 60 GWd/mtU and 62 GWd/mtU rod average for MarkBW and for Mark-B fuel respectively

1The SER for BAW-1 0227P allows burnups of 60 GWd/mtU and 62 GWd/mtU rod average for MarkBW and for Mark-B fuel respectively

cfm6_OOnrc.ppt

Demonstration Of The Ability For The Mk-BW Fuel Assembly To

_ Achieve 62 GWd/mtU Pin Burnup

* Show sufficient data has been obtained to demonstrate accuracy of models to 62 GWd/mtU

* Show that the data is well behaved so that the models are reliable design tools to 62 GWd/mtU

TF o C RA'ATO CM E T E C H M 03 L 0> C- I IE

Justification For Burnup Limit Of 62 GWd/mtU For Mk-BW

"* Data will be presented for both the MK-BW and the Mk-B for comparison

"* Mk-B and Mk-BW are very similar designs that perform in a consistent manner

"* Key data that justifies the new limit "* Fuel rod oxide "* Irradiation experience

"* Fuel assembly growth

"* Shoulder Gap "* Guide tube oxide "* Fuel Rod Reliability

OFRAMAL ,TCM E T E C H N C0 L C> 4S

---

Fuel Rod Oxide No Longer Limits Burnup With M5 Cladding

Maximum Oxide Thickness vs Burnup

-- 0 ----- o.- --

0 0

0 00

1? .0.. . 0• 8 0 0 Zr-4 0 So 0 49 80 l 0 0

0•0 • 0 0 0000 0 0

0 0 6 00

0 10

4k

o North Anna M5M5

10000 20000 30000 40000 50000

Burnup, MWd/mtU

E

U) a)

Ia) Cu .'2_ x 0 X

140

120

100

80

60

40

20

00 60000 70000

T E C H MN o kLTG, M I ES

M5 Has Low Sensitivity To Duty

U.0

Zy4 - 5 cycles 56 GWd/tU

U mu

Eu

U.,.

U E

Eu U

IU

E it

M5 - 6cvcle

0I - ____

0 500 1000 1500

63 GWd/tU*1..

2000 2500 3000 35004000

100

90 1

80-

70-

�V2

4)

60

50

40

20

10

ai1S

IFRA.MATO C E "T E C 1 M C L - : G E

Im

0_

Altitude (mam)

Additional Data Obtained Since Topical Representative Of High

BurnuD CvclesMk-BW Data

0 200 400 600 800 1000 1200

In-Core Exposure, EFPE

1400 1600 1800 2000 2200

J'F RA. M AT C ME T E C HI N O kL G I E S

1T7~

60

50

40

IA

30

20

10

0

Additional Data Obtained Since Topical Representative Of High

Burnup CyclesMk-B And Mk-BW Data

60

501 - _ _ _ _ _ _ _

40

30

20

'OF0_

0

0 200 400 600 800 1000 1200 1400

In-Core Exposure, EFPD

1600 1800 2000 2200

F RA^mA~cr ME

E "0

4 I,1

Ilk qv' Mk-B And Mk-BW Data

Fuel Assembly Growth Data Matches Model

Mk-BW Fuel Assembly Growth Zircaloy 4

0.06

0.05 -... ..

0.03

0.02 1

0.01 ..

0

0 0.1 0.2 0.3 0.4 0.5 0.6

Fuel Assembly Burnup, GWdlmtU

0.7 0.8 0.9 1

T AE M AH T C> MI E T E CH N C LC0 G E S

-j

-J

4) ci

0

I (D

0.04 . ...

I7 Mk-BW And Mk-B Fuel Assembly Growth Data are Consistent

Mk-BW And Mk-B Fuel Assembly Growth Zircaloy 4

0.06 -- ------- • ----------- ___ _. . ._

0.05

S0.04 '"

0.03

,D 0.02 ..

0.01

0 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9

Fuel Assembly Burnup, GWdImtU

FR AýMATO M E T E C H M O L C P I E S

Shoulder Gap Data Well Behaved With Excess Margin Available

Mk-BW Minimum Shoulder Gap Zircaloy 4

2.5000 ...--

2.0001

1.500

1.000 .......

0.500 - . . . .

0.000

0.0 20.0 30.0 40.0

Fuel Assembly Bumup, GWdlmtU

1�1

(U S E

oE

E°E

50.0 60.0

OF RA.MAATC)M E T E C H -4 31C) L. C> C) I E S

-- ---------

10.0

Shoulder Gap Data Well Behaved With Excess Margin Available

Mk-BW And Mk-B Minimum Shoulder Gap Zircaloy 4 ............ .

2.000 . - -..- --

10.0 20.0 30.0 40.0 50.0

Fuel Assembly Burnup, GWd/mtU

2.500

0)

E E r.,

1.500

1.000

0.500

0.000 k

0.060.0

IF RAMATCM E TEC HN 0 L 0 0 I E S

L

Guide Tube Oxide Thickness Data Demonstrates Significant Margin

Guide Tube Oxide Thickness Zircaloy 4

35

30

25

20--

15 . .

10

5

0

20 30 40

Fuel Assembly Burnup, GWdlmtU

50 60

F PRAAAT C M E T E C H M C> L 0 G I E S

0

n 10

------------- -- - -- --------

I ý

Coolant Activity

0

0

0 0

0a

(4ciIgm)

0

ANO

CR3

DB I

Oc I

Oc 2

Oc 3

TMI

Cat 1

Cat 2

Mc 1

Mc 2

Seq I

Seq 2

j

0

+ 0 0

K

0

-U 0 0 fu

0

0I

I>

00 110

I

Failure Rate For Mark-BW Fuel By Year Of Manufacture

1 No Look

U Creep

EL Unknown

U Fretting

N Debris

AN-

Year Of Manufacture

F RAEHMATO cIA E T E C H H• 0, L 0 G I E S

InJI

w

'I

LO 8

6

4

2

0

---1

Conclusion

"* Mk-BW fuel assembly has performed well through 53 GWd/mtU

"* Sufficient data exists to verify design models are accurate to a fuel rod burnup of greater than 62 GWd/mtU

"* Models provide the tools to design a fuel assembly capable of irradiation to 62 GWd/mtU, rod average

I'F RAAhATC>M E T E C H N CD L 01 r-

F Conclusion

" On, the basis of the information presented today the proposed burnup limit for Mark-BW fuel is justified

"1 Define process for obtaining NRC review and approval of the proposed limit

cfm6_OOnrc.ppt