ML20153E339

Summary of 860130 Meeting W/Util in Bethesda,Md Re Program to Develop in-house PWR Transient & Safety Analysis.Official Submittal Needed for Commitments to Schedule.First of Three Topical Repts Expected in June 1986

ML20153E339
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	02/12/1986
From:	Norris J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8602240588
Download: ML20153E339 (34)

Text

.-

T, L .

a , .

February 12 1986 Docket Nos. 50-295 and 50-304 2

LICENSEE: Commonwealth Edison Company (Ceco)

PLANT: Zion Nuclear Power Station, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

REGARDING JANUARY 30, 1986 MEETING ON CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY On January 30, 1986 NRR staff met with. Ceco representatives to discuss Ceco program to develop capability to perform PWR transient and safety analysis for Zion 1 and 2 inhouse. The attendees are listed on Enclosure 1.

CECO gave the staff an overview of their program. Enclosure'2'contains an outline of CECO presentation.

The staff remarked that .in general CECO is-on the' right course, but that no commitments on the schedule can be made in absence of an official submittal. Submittal of the first of three anticipated topical reports is expected in June 1986.

/s/JNorris Jan A. Norris, Senior Project Manager PWR Project Directorate No. 3 Division of PWR Licensing-A

Enclosures:

As stated cc w/ enclosures:

As stated i i PAD-3 (60- .D/PA -

CVogan(M \JNor s;ps 15 Var a 02/g/86 02/d86 Q2/g466 8602240589 ESO212 DR ADOCK 0 5

e ,

L , s

' ENCLOSURE l' MEETING ~WITH COMMONWEALTH EDISON ON REACTOR SAFETY ANALYSIS L

NAME '0RGANIZATION Jan Norris. NRC/NRR Bruce Palagi Commonwealth Edison Kevin Ramsden. Commonwealth Edison-.

Forrest Gunnison Commonwealth Edison Walton Jensen- NRC/RSB Walter L. Brooks NRC/PWR-A/PSB ,

Shih-Liang Wu NRR/PWR-A/RSB Gene Hsti NRR/PWR-A/RSB Jerry Wilson NRR/PWR-A/RSB Peter LeBlond CECO-Licensing c James Watt NRC/PWR-A/RSB , ,

William F. Naughton Ceco - Nuclear! Fall Services' American Electire Power Rad Sharma

• w e

14 1

- i

m .

m, --

=

i L

j, s

, s 'sj { a

~ '

L' <

~

- Commonwealth' Edison' Company- -Zion Station cc: .

Robert J.-Vollen, Esquire _ -Mr. Michael Ca Parker, Chiefo

~

109 North.

Dearborn:

Street Division of Engineering.

Chicago,Illinoisi~60602. , Illinois-Department of Nuclear Safety __ L ~

Dr. Cecil Lue-Hing_ 1035 Outer! Park Drive. 5th Floor

- Director of;Research and Development ' Springfield,-Illinois :62704 ,-

Metropolitan Sanitary District of Greater Chicago , ,

100 East Erie Ytreet <

Chicago, Illinois 60611 Mr. Phillip P. Steptoe Isham, Lincoln and Beale Counselors at Law ,

Three First National Plaza 't 51st Floor

-Chicago,. Illinois 60602 Susan'N. Sekuler, Esquire Assistant Attorney General Environmental Centrol Division 188 West Randolph Street, Suite 2315 Chicago, Illinois 60601 -

Mayor of Zion Zion Illinois 60099 Illinois Department of Nuclear Safety' ,

ATTN: Manager, Nuclear Facility Safety

-  ?'

.1035 Outer Park Drive, 5th Floor

~

_J ~,

r r Springfield, Illinois 62704 U.S. Nuclear Regulatory Commission Resident-Inspectors Office '

4 105 Shiloh Blvd..

Zion, Illinois 60099 ,

y u

Regional. Administrator, Region III '

U.S. Nuclear Regulatory Commission

'799 Roosevelt' Road- ( "$

Glen Ellyn, Illinois 60137 -

M i #

g- 9 / "

h

.I' Y .

ENCLOSURE 2 PRESENTATION ON CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY IJANUARY 1986)

. INTRODUCTION REVIEW AGENDA CEC 0/NFS ORGANIZATIONAL STRUCTURE

/

DESCRIPTION OF CECO VENDOR INDEPENDENCE PROGRAMS

. OVERVIEW

MEETING OBJECTIVES (INCLUDES NRC FEEDBACK) 1 CECO APPROACH (INCLUDES CODES AND TRAINING)

PROGRAM SCHEDULE

^

TRANSIENT ANALYSIS OVERVIEW METHODOLOGY,' CODES USED, AND BENCHMARKING 4

1 CORE THERMAL-HYDRAULICS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING FUEL PIN ANALYSIS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING

SUMMARY

/ CONCLUSION .

PLANNED TOPICAL REPORTS PROPOSED LICENSING SCHEDULE CAUCUS (0PTIONAL)/NRC DISCUSSION s..

O l

PRESENTATION ON c CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY (JANUARY 1986)

. INTRODUCTION REVIEW AGENDA CEC 0/NFS ORGANIZATIONAL STRUCTURE DESCRIPTION OF CECO VENDOR INDEPENDENCE PROGRAMS

. OVERVIEW MEETINGOBJECTIVES(INCLUDN'SNRCFEEDBACK),

CECO APPROACH (INCLUDES CODES AND TRAINING)

PROGRAM SCHEDULE

.i i . TRANSIENT ANALYSIS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING

. CORE THERMAL-HYDRAULICS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING

. FUEL PIN ANALYSIS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING

SUMMARY

/ CONCLUSION PLANNED TOPICAL REPORTS PROPOSED LICENSING SCHEDULE l

. CAUCUS (OPTIONAL)/NRC DISCUSSION l -

L __ -. . - _ - _ ---. ... _ -. --- --

Vice President, Nuclear Operations C. Reed I I Assistant Vice President Nuclear Services N. E. Wandke I I I Nuclear Fuel Services

}. Manager H. E. Bliss I

i Senior NFS

, Supervising Engineer W. F. Naughton I

). Supervising Methods Supervising Nuclear Supervising Reactor Supervising Plant Development Engineer Design Engineer Analysis Engineer Support Engineer C. A. Grier B. F. Momsen B. B. Palagi J. A. Silady.

2

l-Safety Analysis Safety Analysis Group I Group II K. B. Ramsden F. E. Gunnison

_. - . . __ __--_l______-_--___--_--__

d-( &>  ; ,_ hi CECO VENDOR INDEPENDENCE PROGRAMS PWR BWR- ---

-PROGRAM NEUTRONIC' TRANSIENT & NEUTRONIC TRANSIENT &

KEY ITEMS ANALYSIS SAFETY ANALYSIS STEADY-STATE SAFETY-ANALYSIS START OF 1/79 1/83 3/84 10/86 FORMAL PROGRAM c -

~...:,. .

INITIAL'NRC < S/81 1/86 1/87 11/87.

MEETING ,

l ;f -

- BEGIN CYCLE DESIGN 9/82 .

7/86 9/87 3/88

FOR INITIAL USE (ZION 1 CYCLE 8) (ZION 1 CYCLE 11) - (DRESDEN,3-CYCLE 12) (DRESDEN 2 CYCLE 13) 2 (UNIT / CYCLE)

. TOPICAL SUBMIT ' ?? .2/87 9/88 3/89 I

SER APPROVAL 12/83 8/87 3/89' 9/89 i CYCLE STARTUP 2/84 1/88 6/89 2/90 t

i 4

i L. _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _- -

_ . _-- - ~ t -.. - - - .=. s , _ _ _ _ _ _ , _ _ - _ _ _ _

PRESENTATION ON i CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY (JANUARY 1986)

. INTRODUCTION REVIEW AGENDA j

CEC 0/NFS ORGANIZATIONAL STRUCTURE l DESCRIPTION OF CECO VENDOR INDEPENDENCE PROGRAMS

. OVERVIEW MEETING OBJECTIVES (INCLUDES NRC FEEDBACK)

CECO APPROACH (INCLUDES CODES AND TRAINING)

PROGRAM SCHEDULE

. TRANSIENT ANALYSIS OVERVIEW METHODOLOGY, CODES USED, AND' BENCHMARKING l

. CORE THERMAL-HYDRAULICS OVERVIEW >

l METHODOLOGY, CODES USED, AND BENCHMARKING

. FUEL PIN ANALYSIS OVERVIEW

~

l -

METHODOLOGY, CODES USED, AND BENCHMARKING' e

SUMMARY

/ CONCLUSION PLANNED TOPICAL REPORTS PROPOSED LICENSING SCHEDULE -

1 i l

. CAUCUS (OPTIONAL)/NRC DISCUSSION  ;

J 4

4 1

g -

T4+ e -

---ww- -,pce. .--- 1 g w- -- w-nw, y- , ,,,ww --w=a-v weeq- f-ww ,-- yy r+<*-&-1-**+v -- --gy-

MEETING OBJECTIVES CECO ASSUMPTION OF ZION RELOAD SAFETY ANALYSIS' SCOPE OF ANALYSIS PERSONNEL TRAINING BENCHMARKING OF METHODS CONTENT OF TOPICAL REPORTS LICENSING SUBMITTALS 1

OBTAIN NRC FEEDBACK ON CECO PROGRAM 1

'I.

4

- , ~ . . , , , - _ . - , , ,- .c..-.. - .,- _ . . ~ .- ...,,y,- ,r .

v..,,, - - - -

CECO APPROACH 4

DEVELOP RELOAD' SAFETY ANALYSIS CAPABILITY SIMILAR TO .

WESTINGHOUSE PERFORM NEW SET OF ANALYSES FOR ZION USING ,

APPROVED ASSUMPTIONS AND CONSERVATISMS USE COMPUTER CODES AVAILABLE IN PUBLIC DOMAIN AND FAMILIAR TO NRC STAFF i

1 a

,-w -

e.-r .. ,- e.~.r- - , -- , , , y , ,,m,- ,--., - _ -~,. .._,, ... ...-,

^

PROGRAM REVIEW / SCHEDULE' i

i 1982 -

ESTABLISHED G0AL TO PERFORM ZION RELOAD SAFETY ANALYSIS RETRAN-02'AND VIPRE-01 CODES SELECTED BEGAN ACTIVE ROLE IN RETRAN AND VIPRE USERS' GROUPS 1983 -

ZION RETRAN MODELS . DEVELOPED AND INDEPENDENTLY REVIEWED BY EXTERNAL CONSULTANT BEGAN ACTIVE ROLE IN EPRI WORKING GROUP WRITING TRANSIENT ANALYSIS GUIDELINES BEGAN ACTIVE ROLE IN VIPRE PRERELEASE PROGRAM TARGETED ZION UNIT 1 CYCLE 11 (1988) FOR FIRST IMPLEMENTATION OF CECO TRANSIENT ANALYSIS CAPABILITY 1984 -

ZION RETRAN MODEL VERIFIED AGAINST STARTUP TESTS TRANSIENT GUIDELINE EFFORT COMPLETED WITH

, DEMONSTRATION CASES VIPRE CORE MODELS DEVELOPED THERMAL MARGIN LIMIT ANALYSIS METHODOLOGY TESTED 1985 -

RETRAN/VIPRE COUPLED TRANSIENT ANALYSIS i

DEMONSTRATED ACTIVE PARTICIPATION IN VIPRE-UGRA EFFORT FRAP CODE OBTAINED FOR FUEL PIN ANALYSIS

i .

PROGRAM REVIEW / SCHEDULE (CONTINUED)-

1986 -

DEVELOP THERMAL MARGIN-LIMIT WITH VIPRE SUBMIT DNBR SAFETY . LIMIT TOPICAL REPORT TO

. NRC (JUNE)

SUBMIT ZION TRANSIENT ANALYSIS REPORT (NOVEMBER) 1987 -

SUBMIT CECO PWR- RELOAD SAFETY EVALUATION METHODOLOGY REPORT AND TECHNICAL SPECIFICATION CHANGES (FEBRUARY) 1988 -

ZION UNIT 1 CYCLE 11 STARTUP (JANUARY)-

E

--,. - . ~ , - - , . , , - ,. . .# - - - - - - - , , ,e ,

PRESENTATION ON CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY L

(JANUARY 1986)

I

. INTRODUCTION

! REVIEW AGENDA CECO /NFS ORGANIZATIONAL STRUCTURE DESCRIPTION OF CECO VENDOR INDEPENDENCE PROGRAMS t

. '0VERVIEW MEETING ~0BJECTIVES (INCLUDES NRC FEEDBACK)

CEC 0' APPROACH (INCLUDES CODES AND. TRAINING)

PROGRAM SCHEDULE

. TRANSIENT ANALYSIS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING i

. CORE THERMAL-HYDRAULICS OVERVIEW j -

METHODOLOGY, CODES USED, AND BENCHMARKING

. FUEL PIN ANALYSIS OVERVIEW i -

METHODOLOGY, CODES USED, AND BENCHMARKING 4

SUMMARY

/ CONCLUSION PLANNED TOPICAL REPORTS PROPOSED LICENSING SCHEDULE j . CAUCUS (OPTIONAL)/NRC DISCUSSION I

{

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

)

TRANSIENT ANALYSIS OVERVIEW P

EXPERIENCE WITH RETRAN-02 BENCHMARKING OF RETRAN-02 FSAR TRANSIENT ANALYSIS l

L.-

RETRAN EXPERIENCE TRAINING PROGRAM PERSONNEL TRAINED BY CODE SUPPLIER ALL PERSONNEL RECEIVE IN-HOUSE-TRAINING KEY PERSONNEL RECEIVE SIMULATOR FAMILIARIZATION / PLANT SYSTEMS TRAINING PARTICIPATION IN EPRI'S' RASP GUIDELINE EFFORT PARTICIPATION IN RETRAN USERS' GROUP ,

I l

1 1 4

k

N r

P BENCHMARKING OF RETRAN-02 EXTENSIVE INDUSTRY DOCUMENTATION PRESENTED TO NRC IN RETRAN SER SUBMITTAL / APPROVAL CECO BENCHMARKS PERFORMED STARTUP TEST. COMPARISONS (ZION UNITS 1 & 2)

SG MODEL COMPARISONS (ZION /MCGUIRE)

ADDITIONAL COMPARISONS MADE'TO EPRI DATA (MIXING)-

I J

h

- , , . , . . - - . . , , . , . . . , ~, , , , . , , . - - , , , . . - - , -.w.. - - , ., . .. ~ a - , , ,-. - , - - , -

4 CECO BENCHMARKS /RESULTS

- ZION STARTUP TEST COMPARIS0NS TURBINE TRIP FROM 8S% POWER S0% LOAD REJECTION 10% LOAD SWINGS PUMP C0ASTDOWNS RESULT: MODULE PREDICTS PARAMETERS OFf INTEREST. T0 WITHIN INSTRUMENT ACCURACY STEAM GENERATOR MODELING ZION TRIP MCGulRE MSIV CLOSURE (" BYRON" SG MODEL)

RESULT: DETAILED SECONDARY N0DAllZATION GIVES ACCURATE LEVEL / PRESSURE RESPONSE-MIXING DATA COMPARIS0N EPRI THERMAL SH0CK EXPERIMENTS RESULT: RETRAN VECTOR M0 MENTUM MODELS CONSERVATIVELY UNDERPREDICT MIXING IN COMPLEX GE0METRIES

, - , - - , - - - --.-.y m . ..y - , -m-, ., 7- ~ - , . - - - - - - , -r - - y-y . v v

& 7 4 - -- - 4 FSAR TRANSIENT' ANALYSIS VENDOR METHODOLOGY USED (I.E. WCAP 9272)

TRANSIENT CALCULATION PERFORMED WITH RETRAN ,

LIMITING TRANSIENTS ANALYZED COMPLETE LOSS OF FLOW LOCKED ROTOR LOSS OF LOAD LOSS OF FEEDWATER STEAMLINE BREAK ~

RCCA WITHDRAWAL 1

y, , , , _ , , ,. . -.--s.- .._., - r . ~... . ....

1 i

d d

l d

ZION RETRAN MODELS '

SINGLE LOOP REPRESENTATION SYMMETRIC TRANSIENT USE '

FAST-RUNNING FOR LONGER EVENTS TWO-LOOP REPRESENTATION ASYMMETRIC TRANSIENT USE DETAILED STEAM GENERATOR MODELS FULL CONTROL AND TRIP LOGIC BEST-ESTIMATE CAPABILITY CONSERVATIVE INITIAL CONDITIONS j -

102% POWER

, +40F TEMPERATURE UNCERTAINTY 30 PSI PRESSURE UNCERTAINTY THERMAL DESIGN FLOW ANALYSIS ASSUMPTIONS PER FSAR/ VENDOR

PRESENTATION ON CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY-

. (JANUARY 1986)

. INTRODUCTION REVIEW AGENDA

CEC 0/NFS ORGANIZATIONAL STRUCTURE DESCRIPTION OF CECO VENDOR INDEPENDENCE PROGRAMS

. OVERVIEW MEETING OBJECTIVES (INCLUDES NRC FEEDBACK)

CECO APPROACH (INCLUDES CODES AND TRAINING)

PROGRAM SCHEDULE i

. TRANSIENT ANALYSIS OVERVIEW 4

METHODOLOGY, CODES USED, AND BENCHMARKING l

. CORE THERMAL-HYDRAULICS OVERVIEW I

METHODOLOGY, CODES USED, AND BENCHMARKING i

. FUEL PIN ANALYSIS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING

SUMMARY

/ CONCLUSION j -

PLANNED TOPICAL REPORTS

{ PROPOSED LICENSING SCHEDULE

. CAUCUS (OPTIONAL)/NRC DISCUSSION t

i 1

4 J

Ae-n 4

4

- CORE THERMAL-HYDRAULICS'0VERVIEW EXPERIENCE WITH VIPRE-01 BENCHMARKING OF VIPRE-01 4

DNBR LIMIT 4

VIPRE-01 MODEL FOR ZION PWR SAFETY ANALYSIS FSAR TRANSIENT ANALYSIS-j I

i

- , . - 4,, a.- , ,-- - - ,--,,--- , , - .---.,n.

, - , ,. - - - - ~ , - , - , + . ~ - , , - ,. ,. ., , . _ . . - , , r- -

'l i

1 VIPRE-01 EXPERIENCE SER FOR VIPRE-01 REQUESTED BY UGRA MEMBER OF UGRA EXECUTIVE COMMITTEE MEMBER OF UGRA SUBCOMMITTEE FOR VIPRE TRANSIENT ANALYSIS 4

KEY PERSONNEL TRAINED BY VIPRE DEVELOPER, BATTELLE NORTHWEST IN-HOUSE VIPRE TRAINING PROGRAM PARTICIPATION IN VIPRE USERS' GROUP AND EPRI VIPRE PRE-RELEASE AND RELEASE PROGRAMS l

{ PRESENTED VIPRE RESULTS TO VIPRE USERS' GROUP ONE OF THE LEAD UTILITIES IN TESTING VIPRE-01 CYCLE 00 i

l i

o P

BENCHMARKING OF VIPRE-01 EXTENSIVE EPRI DOCUMENTATION PRESENTED TO NRC IN VIPRE SER SUBMITTAL ADDITIONAL CECO BENCHMARKS PERFORMED ZION CORE THERMAL-HYDRAULIC TESTS 1

WESTINGHOUSE BENCHMARKED THINC CODES WITH

THIS DATA PERMITS DIRECT COMPARISON BETWEEN THINC AND VIPRE COBRA IllC - MIT AND VIPRE COMPARISONS I

I i

6 DNBR LIMIT SPECIFY FUEL TYPE OF INTEREST WESTINGHOUSE OPTIMIZED FUEL SELECT CHF CORRELATION EPRI CHF CORRELATION i

W-3 CHF CORRELATION

. IDENTIFY CHF EXPERIMENTAL DATA BASE EPRI DATA BASE CONTAINS WESTINGHOUSE DATA i

WILL USE SUBSET OF WESTINGHOUSE DATA APPROPRIATE FOR ZION FUEL bEVELOP VIPRE MODELS FOR EXPERIMENTAL TESTS AND PERFORM ANALYSES i -

PERFORM STATISTICAL ANALYSIS OF VIPRE RESULTS t

l l

t I

1

a t

VIPRE-01 ZION MODEL l

ONE-EIGHTH CORE MODEL' INCORPORATE WESTINGHOUSE ASSUMPTIONS LIMITING AXIAL AND RADIAL POWER DISTRIBUTION-HOT CHANNEL FACTORS

• DECREASE FLOW TO HOT BUNDLE BY FIVE PERCENT i -

CONSERVATIVE INITIAL CONDITIONS I

)

l-

)

t 1

k

,-- , ,. ,,---.v.--, ,---,-----.y,-,--~.---%- . , - . . .-- -r--,- -.-- - ., 4 .---e , - ---,----y , ca.q-+, ...y--.

FSAR TRANSIENT ANALYSIS FOLLOW WESTINGHOUSE METHODOLOGY FOR FSAR TRANSIENT ANALYSIS USE RETRAN TO DEFINE TRANSIENT B0UNDARY CONDITIONS i

PERFORM CORE THERMAL-HYDRAULIC TRANSIENT ANALYSIS

TO OBTAIN MDNBR VERSUS TIME COMPARE TRANSIENT RESULTS WITH DNBR LIMIT j

3 b

)

PRESENTATION ON CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY (JANUARY 1986)

. INTRODUCTION REVIEW AGENDA CEC 0/NFS ORGANIZATIONAL STRUCTURE DESCRIPTION OF CECO VENDOR INDEPENDENCE PROGRAMS

. OVERVIEW i

MEETING OBJECTIVES (INCLUDES NRC FEEDBACK)

CECO APPROACH (INCLUDES CODES AND TRAINING)

PROGRAM SCHEDULE >

. TRANSIENT ANALYSIS OVERVIEW i -

METHODOLOGY, CODES USED, AND BENCHMARKING

. CORE THERMAL-3YDRAULICS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING

. FUEL PIN ANALYSIS OVERVIEW METHOD 0LCGY, CODES USED, AND BENCHMARKING

,t

SUMMARY

/ CONCLUSION l

PLANNED TOPICAL REPORTS l

PROPOSED LICENSING SCHEDULE

. CAUCUS (OPTIONAL)/NRC DISCUSSION r

--,,--ew ~  % - ----,---,g '-+ - - - - - * --e, ,----w,-wri. - ~ , * - ,. w ---w---r=---.wrw 1*w - - - . .ys- - -y,-7.,ey **.

• w - g* ---cv-- m-w- --,,

h

't i

4 FUEL PIN ANALYSES OVERVIEW i -

REASONS FOR FUEL PIN ANALYSES i

I -

DEVELOPMENT OF FSAR FUEL PIN TRANSIENT ANALYSIS ,

J t

e 4

1 l l 1

4 i,  ;

4 i

i

) l l

A I l

! l 1

1 i

4

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

REASONS FOR FUEL PIN ANALYSES TWO FSAR TRANSIENTS REQUIRE DETAILED FUEL PIN! ANALYSIS-

- LOCKED ROTOR --- PEAK-CLAD TEMPERATURE LIMIT

- CONTROL R0D EJECTION --- STORED ENERGY IN FUEL PIN LIMIT

&2 a sa, 1

FUEL PIN FSAR TRANSIENT ANALYSIS f -

DEVELOP BASIC FUEL PIN MODEL 1

PERFORM PARAMETRIC AND BENCHMARKING STUDIES TO DEMONSTRATE USED IN MODELS ARE CONSERVATIVE INCORPORATE WESTINGHOUSE ASSUMPTIONS PERFORM FSAR TRANSIENT ANALYSES

)

i i

I i

4

'f I

l l

l

9 PRESENTATION

! ON i CECO PWR TRANSIENT AND SAFETY ANALYSIS CAPABILITY (JANUARY 1986)

. INTRODUCTION

{

REVIEW AGENDA '

CECO /NFS ORGANIZATIONAL STRUCTURE DESCRIPTION OF CECO VENDOR INDEPENDENCE PROGRAMS l . OVERVIEW j MEETING OBJECTIVES (INCLUDES NRC FEEDBACK)

CECO APPROACH (INCLUDES CODES AND TRAINING) 1 PROGRAM SCHEDULE l

j . TRANSIENT ANALYSIS OVERVIEW

[

METHODOLOGY, CODES USED, AND BENCHMARKING

) . CORE THERMAL-HYDRAULICS OVERVIEW -

METHODOLOGY, CODES USED, AND BENCHMARKING l . FUEL PIN ANALYSIS OVERVIEW METHODOLOGY, CODES USED, AND BENCHMARKING

) .

SUMMARY

/ CONCLUSION l l PLANNED TOPICAL REPORTS PROPOSED LICENSING SCHEDULE

. CAUCUS (OPTIONAL)/NRC DISCUSSION I

i

, --<-r --.,,,,,,,- _ , - - -- ,_--+ ,,-- - - ,-4+-- ,-------,,,----.-m,--_. ~,,--. .#--, ,

PLANNED TOPICAL REPORTS DNBR SAFETY LIMIT TOPICAL ESTABLISH DNBR SAFETY LIMIT FOR ZION FUEL USING VIPRE CODE AND EPRI CORRELATION - JUNE 1986 ZION TRANSIENT ANALYSIS TOPICAL ESTABLISH ANALYSIS OF RECORD USING RETRAN AND VIPRE - NOVEMBER 1986 CEC 0 ZION RELOAD SAFETY EVALUATION METHODOLOGY REPORT ESTABLISH METHODOLOGY TO PERFORM 50.59 EVALUATION OF ZION RELOADS - FEBRUARY 1987 n

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

1 PROPOSED LICENSING SCHEDULE 1 DATE ACTION SER APPROVAL 1/86 MEETING TO DISCUSS ZION SAFETY NONE i ANALYSIS PLANS 6/86 SUBMITTAL OF 710N DNBR SAFETY LIMIT 10/86 TOPICAL REPOR' 11/86 SUBMITTAL OF ZION TRANSIENT ANALYSIS 4/87

, TOPICAL REPOR' 2/87 SUBMITTAL OF CECO ZION RELOAD SAFlETY 8/87 EVALUATION METH030 LOGY 'OPICAL lE )0RT AN ) TECH 11 CAL SO ECIFICA" ION CHA WG'ES 1/88 ESTIMATED STARTUP 0F FIRST CYCLE TO NONE REFERENCE CECO TOPICAL IN CEC 0 RELOAD "50.59" LETTER i

, , , - - - . . - . -. , ,.,_,_.._,-..,___..,_.._...-.m.

MEETING NOTICE DISTRIBUTION OPERATING REACTORS BRANCH N0. 1 DIVISION OF LICENSING entral File L PDR PAD #3 Rdg '

ORAS H. Denton S. Varaa J. Norris OELD E. L. Jordan B. Grimes Receptionist ACRS (10)

Resident Inspector Regional Administrator N. Olson C. Vogan NRC Participants W. Jensen W. Brooks Shih-Liang Wu G. Hsii J. Wilson J. Watt O