MEMORANDUM FOR:

FROM:

SUBJECT:

January 28, 2000 Stuart A. Richards, Chief Project Directorate IV and Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Steven D. Bloom, Project Manager, Section 2 Project Directorate IV and Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

/RA/

SUMMARY OF MEETING HELD ON DECEMBER 7, 1999 WITH WESTINGHOUSE ELECTRIC COMPANY TO DISCUSS THE WESTINGHOUSE FUEL PERFORMANCE UPDATE

The NRC staff met with representatives of Westinghouse Electric Company on December 7, 1999, at One White Flint North in Rockville, Maryland for a Westinghouse Fuel Performance Update. Attachment 1 contains the list of attendees at this meeting. The handouts used by Westinghouse during their presentation were proprietary. Attachment 2 is the nonproprietary version of the slides.

Westinghouse's presentation contained four major topics of discussion. The first topic was lead test assembly (LTA)/Ilead use assembly (LUA) programs and fuel inspection plans. Westinghouse provided a summary of ongoing LTA programs and ongoing or planned fuel inspections. Next, Westinghouse gave an update on the top nozzle holdown spring fracture issue. The update included a root cause analysis, and immediate and long-term corrective actions. Westinghouse discussed the top nozzle holddown spring screw licensing option which they are developing. This option would allow re-insertion of assemblies with fractured screws, provided design and safety criteria are met. The NRC staff indicated that this approach may be appropriate providing all the necessary justification and documentation is provided. The last portion of the presentation dealt with the Westinghouse improved performance analysis and design model (PAD 4.0). The presentation included a brief chronology and overview of their final submittal, a review of the last outstanding request for additional information, question number 9, a review of instrument fuel assembly (IFA) - 432 modeling, overall PAD 4.0 conclusions, and potential impact on the legacy fuel. Westinghouse emphasized the importance of this review and requested that the NRC provide dedicated resources to ensure that this review was completed in a timely manner.

Project No. 694

Attachments: 1. Attendance List 2. Nonproprietary Slides

cc w/atts: See next page DISTRIBUTION: (Hard Copy) File Center PUBLIC PDIV-2 Reading SBIoom OGC ACRS

E-Mail JZwoli nski/S Black SWu MChatterton RCaruso

*Note document needs to be scanned

To receive a copy of this document, indicate "C" in the box

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NAME SBIoo 4 ' EPeyton JW miel SDembek•.,

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UNITED STATES NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

January 28, 2000

MEMORANDUM FOR: Stuart A. Richards, Chief Project Directorate IV and Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

FROM: Steven D. Bloom, Project Manager, Section Project Directorate IV and Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT: SUMMARY OF MEETING HELD ON DECEMBER 7,1999 WITH WESTINGHOUSE ELECTRIC COMPANY TO DISCUSS THE WESTINGHOUSE FUEL PERFORMANCE UPDATE

The NRC staff met with representatives of Westinghouse Electric Company on December 7, 1999, at One White Flint North in Rockville, Maryland for a Westinghouse Fuel Performance Update. Attachment 1 contains the list of attendees at this meeting. The handouts used by Westinghouse during their presentation were proprietary. Attachment 2 is the nonproprietary version of the slides.

Westinghouse's presentation contained four major topics of discussion. The first topic was lead test assembly (LTA)/Iead use assembly (LUA) programs and fuel inspection plans. Westinghouse provided a summary of ongoing LTA programs and ongoing or planned fuel inspections. Next, Westinghouse gave an update on the top nozzle holdown spring fracture issue. The update included a root cause analysis, and immediate and long-term corrective actions. Westinghouse discussed the top nozzle holddown spring screw licensing option which they are developing. This option would allow re-insertion of assemblies with fractured screws, provided design and safety criteria are met. The NRC staff indicated that this approach may be appropriate providing all the necessary justification and documentation is provided. The last portion of the presentation dealt with the Westinghouse improved performance analysis and design model (PAD 4.0). The presentation included a brief chronology and overview of their final submittal, a review of the last outstanding request for additional information, question number 9, a review of instrument fuel assembly (IFA) - 432 modeling, overall PAD 4.0 conclusions, and potential impact on the legacy fuel. Westinghouse emphasized the importance of this review and requested that the NRC provide dedicated resources to ensure that this review was completed in a timely manner.

Project No. 694

Attachments: 1. Attendance List 2. Nonproprietary Slides

cc w/atts: See next page

Westinghouse Owners Group

cc:

Mr. H. A. Sepp, Manager Regulatory and Licensing Engineering Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230-0355

Mr. Andrew Drake, Project Manager Westinghouse Owners Group Westinghouse Electric Corporation Mail Stop ECE 5-16 P.O. Box 355 Pittsburgh, PA 15230-0355

Mr. Jack Bastin, Director Regulatory Affairs Westinghouse Electric Corporation 11921 Rockville Pike Suite 107 Rockville, MD 20852

Project No. 694

MEETING WITH WESTINGHOUSE ELECTRIC COMPANY

WESTINGHOUSE FUEL PERFORMANCE UPDATE

ATTENDANCE LIST

December 7, 1999

Organization

S. Wu M. Chatterton R. Caruso S. Dembek K. Hoskins B. Hommerson D. Koontz D. Rowland S. Ray D. Colburn S. Ferguson P. Larouere B. Herwig

NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DSSA/SRXB NRR/DLPM/PD42 Westinghouse Nuc Fuel Business Unit Southern Nuclear Duke Power Westinghouse Westinghouse Westinghouse Wolf Creek Nuclear Virginia Power SCE&GNC Summer

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This is the second Fuel Performance Update Meeting held between Westinghouse and the .NRCn1999. It had b.eenr..equested by the NRC to hold the meeting semi-annually vs annually and to:' f"6O•,~~•ous onselected

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Background ............. . ... ..' ... ..

Joint Material/Mechanical Design in use since late 1970"s (17x17).

........... • Early 1980s - [ ], c fuel assemblies with fractures in [ Ia, c fuel: - Improved and standardized screw design for all 12 foot fuel assemblies. - No design changesi or :issuessince 1,•984. .........

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fractures observed: . - Assemblies re-nozzled.

Presumed root cause was over-torque [ .. c

Late 1998 - [ ], c fuel assembly (14f6otiidesign) with fractures observed - Assembly discharged.

Root cause indetermint ..e......

* Early 1999 - Significant fracture rate found during outage inspections.

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120f..u~el :a~sse~mblies:..wer:,npte codiio. were... inp-e durin the.... fall....

New spring screwi:nspection ' technique: ..... ... .... .......... ii~ i~ i~ ! ii : !! i i~ : :: : :: .........

- Provides greater discrimination o:f ft ures c.I0aompred to visual exams.Uses a [....... ac S... ...::: ":" ii:iii iii ::i •!• !!! .......... .....

Repair activities have not affected critical path, todae•' ,. S.... ::~~ ~....,..............•,':: ''

* Fractures identified in fuel built prior to.iw ndow: a b,:..

- Single fuel ass::semblies at [ . abc. - Multiple fuel assemblies::at [.1a, b,c

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4o fractures detected in susceptible region at a 17x7pla....t:':':'•::•:.:';' '•*•'•::': ....... :.:...: :::.. ................ -.............. ::...... ." .:::'•:"• ....

Screws used idiffe nt [. b, .

4o fractures obsered,,in liX fuel [ ]L•i b:c ofrcue o in..... 2X.... .3aata

4o fractures obseived in 1X. 2X. or 3XT:f :la a 14 foot design nlant "•::%'"i"iil i

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- Expect fractures in several plants. - Plant-by-Plant.,:: ,inspection, repair/replacement, and contingency

plans being developed........ S.. . . . . . . . . . . . .. ...........' '... .

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* Working with WOG ..todevelop.ontingency option to reinsert fuel assemblies with fractured screws provided!tIhatdes.s.ign & safety cilteriaare met.

1217/99 1112/7/99 11

.. .. ....... .. . . . . . . . :......... .............. ........ ' " .. .... ...•i~iillliii! :

Top N o zzl e S crew Summa ry

R oot cau se co m p leted on sch ed u le. .............................. ...................................:......................... - Customer Summary Letter November 1999 - Final Report.December 1999

..Fall outage inspetionscompleted..........

S Spring 2000 outagepans underway. ....

• Improvements with current material inl]!ace. ":•:'iiil,'ii!ii!,iii••; - Next step moiofied [ ] screw. .

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........... ...... * ......... ............. ........... ........................................ ............ ini-m in g cwll

.............. .... . .......... -............. ......... .................... .... ................................ ....... ................................................................. . ...... :.: .. .......

• Westinghouse be:lievesthis:: optionis,,:S..... needed to provide additional ... ...... .. : : : : : : : : : : : : : : : : : : : ........ ..

flexibility: Expects to :be applied. on a plant specific basis depending on",; th6 situation.

i ii iii !!!i !!! !iii iii i!! !!ii !• , ... ... " ......... '""•• i~iiiiii~iii~~i~liliii~iiii~iiiiiiiiii.....:. ....... "':::• ~ ~ ~ ~ ~ ~ ~ ~ ~ ......... ... ".•.::!:...•...

~~.. ................ iiiii•...!•

: : : • i i~ i " ! i i i i i ',i~ i i i i i~. ........ . ....... ...,....,...

12/7/99

Key Design/S afety Criteria to S:uppor•fic'ensing Option

• Detailed visual ins.p~e.ction of ....... ..............

* No clamp gaps [ c allowed for re-inserted assemblies: • i i . ......!i ! !! • • ii ~ : : :: ::.... .......... .

- Ensures all parts are secud t:':::the top: ntheto:zle. .n.o.zze....

- Ensures no operations or handling concerns. ..... .....

....:::•:i!!!ii!!• ....

plant specific loose parts assessment will bepi-ibPormed to ensure that .. .....

......ii:iii!::::::::

:: ::

the specific nozzle idesign has been evaluated. ................ a l a t o n s •,• ,.~

A plant specific... reactor internals :hlddown capability evaluation is performed to address::: -sof holddown forceI forthe affected assemblies.

• Licensee tracks non-conforminri*g i::;condition in its intenal deficiency tracking system as per Generic Letter 91-18, Revision 1.

12/7/99'. 4

S.. .. ... .... .. ...... ...... . . ...... .. ... .. .. ..........: i i i

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............

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... ...........

S..... ::::::: :............

.................... ii!

:: :... .... -.... . .. . .

Westinghouse Improved Perfonrmance :Analysis and- DesigMn M del ****.***..****

(PAD 4.0) ....... :;..... ... .... ..... • ii~:iiiiiiii•!!

Fu.e..... ....... ••........ ........

Dece.m.ber ...1.999 .......

i~iiiiiii~iiiii~ii~ii .... ::"i~iiiii~i......... iiiiiii....... ii• ....... ............ ~!!•ili~i'i~i

Pr.....esented by:....... .....

..::•!i~~~~~~~~~~~i.. ...... .... ........iii! iiiii~ ii~iii~!ii~~iiiiii S...........~. .. :.:.. :.:.:.:...

WilliamH, iSlagle

1 2 / 7 / 9W..N.-.op ie t a r y. 3.1

12/07/99 ~~~~~~ ~ ~ ............. ...rorear ........... .... •iiii~iiiiii!ii...

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......

. .... ........

.. ........ .

............ ............

............

The PAD topicalreport- review and approval is

currently viewed as the most. citicaltjopical report on::Westingho:use's review agenda.

"12•/...9...

'...

.......... S. . . ..... ...............;

" :• ! • !!: . ""::•.............i.

12/07/99

... .. :: ::........'.....!: :;.. .

Agenda for Presenton :::::::::,... .. ... ... ..........i! ! • i~ i ii i i :: :::.......... .............: :: ::: :: .............

.... .. . . . *. .*.~ .. *.* .** * . . . ...... . . .*.. . .. . ...

* Brief Chronological Overview * Brief Overvie.-w ,ofFinal Submiftal Package

S.............. : .. . . .. i i i i i i : i i i i i i .i i •.•: :........== = == = == = == = = == = == = ........... .... .....:: i ii • i ] :: : : : . . .

* Review of RAI #9 (Typical PloIs) . ° Review of IFA432.:Modeling

* Conclusions :....... .... .... .... ... I m p l ............... ementa~~~lon•,&&egacy Fuel .............,,,,,,,,••... S.... :: :• iii................... S....:::• !~ i~ii i•:::......... ............ . "... ..... * Implementation':::'*:*::: ..:&::Legacy Fuel

Schedules ...

12/07/993

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to c UIVd TfT3UT* TUI~OU o1Jd ST loppow UO!SOJJO ON -~

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• 11/97:

12/07/99

Brie ~.............~e~i

Brie~f :Chr~o~nol~ogical: Ovierview

' ........... . .... . . ........" ': ....'::: :.: . :: : ::. .:.

Incorport:"a"*tiýoýýýýn l"of Z*rBA int YPAD 3.4 "and its"associaed feedback affects result in further reduction to RIP margins, l;ead::I n toprojiections of "Gap Re-Opening". - Westinghouse issues an Industry JCO to the NRC that

addresst:e-s- Gap ReOeing. ad dreS!•es~~~i'G a~~i•R e -O......... ........... ....: ............. :::'~ /••l il•~iii!~~ii;•ii,•

- Westinghouse's assessments:tates: ::that the Safety Significance is consi~d~ered low.

- All reload alyses are done with the interim PAD`- li:moNdel that . ....... :i:..,.," ::.t..........

incorporates ZrBA and gapg e- p opening methodology.

Westinghouse commits to upr'date .. PAD to resolve gap reopening.

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.ii .... .. .... ..... . ........ ..

† † † † † † † † † † † † † † † † † † † † † † † † † † † † † † † * .*.* . *• .....:.:.• i. Bief Chonlgia .Ovevi

Brief Chronol~o. ui.at •,Ve6'ý"""" iw .: : : : : : : : :: : : : : : ::.......... ,. ..............

• 01/98:

* 06/98:

12/07/99

NRC acc::::ept:::::s** W...estiLngouse's- appoac for Gap '... /

Re-Opening. J c o............. :.............. ........:::: ::::::.... :........ t . ......e: : p " 1 : ; w: : ................. .s p c i i e d i n t h

Complia-nce..wth 10 CFR 50.46 must be demonst ed,' . ........... .....:: • i i!iiiiiii•!!•:?• •ii~ ~ii•• • ........... :•:•••:'

Westinghouse submits WCAP-1506" .P.. "Westinghouse""•n•4Reactor Creep Model".

Revised In-reactor irradiatifn cIreep model. r ". ...... .

- L "':- [!•:..] '':i~i~ii i:.

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Brief Chronol :g ... .o: i-waiii: Ve:::::rview ............... ..... ..............

• 01/99:

* 06/99:

12107/99

Westinghouse provides supplementa respons0 •toRIs'.

Westinghouse. providesadetailedpresentah............. S. ... ...... : .......... . ......................ii~ i i~ • ! !! :: . .. .. ..

Westinghouse p~r" ..o* .v'::'Ide'es :;::•"'detailedm,:,re•sentation to the

S..... .. :: ::::: ::::: :::::................ NRC on Westinghouse's [*m .. ; L i............ ... .... ' ':: ! !•....

- NRC r uests that Westinghouse submits!iia::..re-write of the ............ iiii•i••:, .. ..

WCAP to:::::tinc..daethe original submittal and t other model changes.

- NRC request~s that Westinghouse "i propose [ .a, c

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,..............'i!:iiii:$:;:........,...

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* 11/99:

* 12/99:

12/07/99

Brief Chronological Ov erview......... . . . . . . . . . . .~o ... .... .

W estinghouse ......submits final .......... a........ package .... for P D ..... 4.0 according to agreement established during 9/99 phonecall. S. .. .... .................. :i: i iii i i£ :i: ; ; i i i i i ii i i i• , , , , , ,, • , ............ .. .

- Westinghouse comples withn•request ...to ,incororate all the ~~~~~~~. :•:• ~ i:i!:i!•!!: ... ....... - . .

[ ]a b, c intoa single[ •; ~.... ...........

•!•i•!!i•!!!!!!i!!!!!i.................

Westinghouse complies with requs Ito proyide [

i~•.......... :.......::::•ii~!::!!• • ...

Follow-up meeting with NRCeto review final submittal package, discU:ssthe review schedule. and requested

SER language with regards to "Legacy Fuel"::..

10 .....i! . ..... .......

I

S.... ..... . :: : :: i i • : :: ..... .. ..... .:: : : : : : :: : : : : ::........ . . . . . .. . . .. : : : :. . .. B rief.......... .............b a[ ac ag

The final submittal package icd fieat ... chment:

* I

...:::: : :: : : :: ::............ : ............. " .. ................... ..::::: " • 'V'! !' " W !!'. ::.... ..... •1

Re-write of WCAP15O63P "Westinghouse In-Reactor Creep Model" to include "Other Model , C: .h.ges,,,,

WCAP-15063-P Errata for'c-66ections noted to the NRC in respo.ns.es .to.: other RAIs.

Response to last outstanding question (RAI #9) on PAD;:..: S... .....' .... ....... 1 Model:R'e.visions submittal. Also i-n6cluded are five external independenti a'ssessments of Westinghouse's creep model by industry experts.:"'•iiiii•,,,:.

.............

Attachment 1:

Attachment 2:

Attachment 3:

12/07/99

Brief Overwie.w....•o~f:,m*.al•--.:;SU,Su m•'=:'='=:''=''' .............e ...: .. ................ .. ......... .......

Attachment 4:

Attachment 5:

12107/99

on the latest model revisions requested during the review process:: Also included is the IFA-432 modeling

comparison requestedbyIt'h"eI' :N reviewer.

Discussiono�fP:o A!Hf D4::0 .. imp.lementation and approach on S.•. i•: !!!i ii!i • :_! • :::: .............

"Legacy Fuel". S... . :: q • i• L-' • ?::• :::• -:-:...

12

~~~~~~~~. . ... . . . . .. . . .. . ...... •...,

Review of RAI.#9.

* Original request (9198) covered typical performane aeas: lots of

corrosion vs burnup, clad OD vs bumup, centerline temperature vs power and bumup, rod pressure vs bumup, and power vs burnup.

I ; ; I I I........ 11........ ...... . ..

............. :: :. .. , , .. .

• Significant additional information requested and transmitted:tv:-, ...............-... ,• • ..:.:..,.,.

- Equivalent PAD 3.4pa comparison plots (6/99); - Upper bound rod pressure vs bumup i of(.IBA...and Non-IFBA fuel)

(6/99); - Typical fuel centerlin em"" peratures used for nuclear safet yses

(6/99); - Input parameter:su:'sed in the modeling of the tyical plots that will be

used to conduct an aud'i: c•c.alculation with FRAPCON-3 (6/99); and ' ..:: i lg!......"..ii,:i!!:i ..

- Overall swelling rate and creep :rate model uncertaiti•es (9/99).

12/07/99 13

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..........6# IVI O.. .X....A.. ...... .... a

Review of IFA-432 Modeling

Original request (11.98) for..informal PAD4.0 modeling •4f• 9thffe A432n:

fuel assembly, rods 1, 2, 3 and 5. Used to help . evaluate conservatism of fuel performance thermal

models (fuel tempieratres vsbumup).. These fuel rods have been modeled in the past by.Wes ing•house,,., G e e a e p ' .................... . 1 L .... •.:•N°•ii:: .A

-Generated a specia version :of PAD 4.0 for IFA-432 modeling an. : S. ..: : : ! ! i ! • ! • ! ::.. .... ...

provided informal results (3/99). .... .. - In responseto reques:t to assume no fission gas it'...Ileakage, and

m a "....iiiii•!...... • ý ý••" .. ta, b, c incorporate an alternat approach to creep model [ .. ., "........... .... . : ::i:i:ii'i• ..

IFA-432 analy~sis re-performed affdf presented to the NRC (6/99). Final re-analys"is pirovided in submittal to igiiincorporate all PAD 4.0 model changes (11/99).

12/07/99 i 15

91 661LO/Zi

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(po~qu si aoox Iua; OU Giua llo

........... ++ ++ ++

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............... i":+ '+ i~ii'iiii~iiii~iii++• ...... '..................

....................... p .... ......... . vUII3PN WJ J A

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S.. .. ............. •! i: •= . ..

.: . .. . . ...

•i!•! • i~~~~ii ~~.................. .......... .. ......... +, ++ ! iii!j ~ i iij ii•+

... Conclu..sions: ...............

PAD 4.0 upgrade better reflectsin-reactor +performance anedfuel material behavior.

- The revised models have been calibrated to both the previous databases and newdata.•. databases~~~!IN++,.+.: an.............''.......t ..a ............

The unchan.ged models have been re-calibrated the¥prv .us..

databases: (and" r"evised I..FA-432 data) and remain applicable. Rod internal pressure margins improved .. i"expected [

ab, c

Unchanged models (I:.:'6!1!iefission gas and thermal) producer"esults consistent with previously lic gnse a..versions, as expected.

1..........1.

: •i~i ilili ::. ':::•:•i~ii.. ...........

"":...h........:.:... : iii~ i i!. ':•:ii........ ...

.:::::::. • ...........~~ ~~~.............. .... .. .. ................... . ... ..... ..... ..... ' i ii~ i+,

12"07/" 17

S.......:: : ! • ! ! ! • i i : :•....

information exchange/dialogue and numerous iterations with the NRC to ensure all reque•sts were addressed.

~~~~~~~~~~~.... ................iii~ ~i~ ii~ iiii ! ........... :......., .. ...............i!!! i.".-il...• :::........

*PAD 4.0 fulfills :,th~e commitment to the NRC to udte •"':th~ fue performance anaytc mO s.........

1..0... ..............,...

............ ' "":' '.ii! i•• .. ..

...... ...... ",::!:ii-i:iiidiiiii:u.s.

Th final!!!: •u cu .:ato :::::::f.:::::.. i i

inor aio xcagedalge n nu eru itrtin w::•ith the N:R:.

"toii~i: enur all':'': 'eyss:weeadesd

...........

S...... .... !~~i!i!!•:•... . -.-•:'.: ...

....................... i~~iiiii~ii!!•~~iii~••i~~i ! :

Implementation & egacy Fuel .......... ............. . .... :: ::.. ... .....

Proceed with implementation of PAD 4.0 on a forward-fit, basis consistent with the plans being developed .between Westinghouse .andhe. WOG.

Establishing pp"o*priate dooumentation and training.

As noted in prevlous ýmeetings ,with the NRC, PAD 4.0 may still predaic•t.:"."• some gap re-opening in "Legacy Fuel"::::-. W•W...estinghouse will demonstrate that these assemblies will continue to meet all sa fey limits as well as 10 CFR 50.46 oxidation imit-s.Gap re-opening Legacy Fuel wll continue to be covered by the JCO metho•o•lo .until permanently discharged.:::.::,:

12/07.99 .....

12/07/99. ::i 19

............. ... ..... ii!!:''"..:iii:. ..

S. . . . . . . . . . . : : : : : ! ! ! ! • ! i ~ i ~ i : : : : : . .. . .. .. .. ..:: :..'. .'.. ..........: :.'.

S.........................................

11/19/99: Westing-house:'s to f.nalubmt..

Based on previous ver(balcom itments, it was stated that the NRC's reviewer would be able •... ...................... :::........ I ...... ! : : ::. .. o.... , to complete his review::and: is •a T•R th-in :30:daysfter recei g the final submittal. It was further stated that the NRC should be able to issue 'a.n SE iih'i- dqa.safter receiving the TER from the reviewer. It is extremely important to Westinghouse and our customers

that the following schedulesare m.et: ...

01/15/00: NRC reviewer issues Technical Evaluaon Repor (TER) S.... :a:::a t iW!ie ,PiP r::.. ( i:E:•..)

02/15/00: NRC issues SafetyEvaluation Report (SER)

12/07/99.. 20 • '": i~ii i• !•i !!i!.... . "•: ';,...........,,.

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