ML17219A269

Summary of 861119 Meeting W/Util & C-E in Bethesda,Md Re Use of gadolinia-bearing Fuel & Planned C-E Topical Rept to Justify Use.Meeting Agenda & Viewgraphs Encl

ML17219A269
Person / Time
Site:	Saint Lucie
Issue date:	12/02/1986
From:	Tourigny E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8612170136
Download: ML17219A269 (41)

Text

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'0 0 oEc s 1986 Docket No. 50-389 LICENSEE:

Florida Power and Light Company (FP8 L)

FACILITY:

St.

Lucie Plant, Unit No.

2

SUMMARY

OF NOVEMBER 19, 1986 MEETING WITH FP8cL, CE, AND NRC STAFF REGARDING USE OF GADOLINIA BEARING FUEL IN UNIT NO.

2 Introduction NRC staff met with FP8L personnel and Combustion Engineering (CE) personnel on November 19, 1986 in Bethesda, Maryland, to discuss the future use of Gadolinia bearing fuel in Unit No.

2 and the planned CE topical report to justify such use.

The meeting was chaired by the NRC Project Manager for St.

Lucie.

The agenda for the meeting is contained in Enclosure 1.

Enclosure 2

identifies the meeting attendees.

A summary of the meeting follows.

~Summer Mr. J.

Perryman (FP8L) stated that FP8L plans to use Gadolinia bearing fuel in Unit No.

2 beginning with Cycle 5, estimated to start in May 1989.

In addition, Gadolinia bearing fuel is currently being used in Unit No.

1 (Cycle 7).

Gadolinia bearing fuel (GD203-UO ) offers two major advantages over non-fuel bearing poison rods (B C-AL 3 ).

The first advantage is reduced average l.inear heat generation kate )L]GR).

The fuel rods operate further from Departure from Nucleate Boiling and LHGR;limits.

The second advantage is increased uranium loadings.

This allows lower assembly average enrichments, thus lowering fuel cycle costs.

Mr. Perryman's passout is contained in Enclosure 3.

Mr.

E. Trapp (CE) presented an overview of the planned topical report.

He also presented an overview of the lead test assembly (LTA) program currently being conducted at Unit No. 2.

These overviews are contained in Enclosure 4.

There are currently four LTA's operating in Unit No.

2 (Cycle 3).

Each LTA has eight Gadolinia bearing fuel rods with eight weight percent (w/o) Gadolinia.

Natural uranium is the host fuel.

The topical report will contain the following sections:

introduction, methodology, benchmark analyses, licensing applications, and conclusions.

The staff felt that the topical report overview covered what they would expect to review and made the comment that more work may need to be performed on the benchmarking analysis, in light of the fact that FP8L plans on loading a whole batch of 8 w/o Gadolinia bearing fuel for Cycle 5.

8612170136 861202 PDR AQOCK,05000389 P

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Mr. J.

Perryman then presented the Gadolinia topical report review schedule, as envisioned by FP8L. It is expected that the topical report will be submitted to the staff by April 1, 1987.

FP8 L would like NRC approval by December 31, 1987.

The details of Mr. Perryman's schedule are contained in Enclosure 5.

Enclosures:

As stated cc w/enclosures:

See next page I:

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G. Tourigny, Project Manager PWR Project Directorate ¹8 Division of PWR Licensing-8 PBD¹

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Enclosure 1

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NRC/FP8(L/CE MEETING ON GADOLINIA TOPICAL REPORT NOVEMBER 19 1986 Name Ed Trapp Chuck Molnar Ivan Fiero Paul Gavin Ed Weinkam Ed Knuckles Jimmie Perryman Carl Beyer Richard Lobel Dan Fieno Cecil Thomas Ed Tourigny Affiliation CE St.

Lucie Nucl. Fuels Project Manager CE Licensing CE Fuel Engineer ng CE Fuel Engineering FP8L Licensing FP8 L Core Physics FP8L St.

Lucie 2 Fuel Project Coordinatot PNL NRC Consultant NRC/DPLA NRC/DPLB NRC/DPLB NRC/DPLB

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Enclosure 3

FPL PLANS USE OF INTEGRAL FUEL/ABSORBERS IN ALL NUCLEAR UNITS ST, LUCIE 1, CYCLE 7 CYCLE 8 4 w/o GD, 2,70 w/o U23~

8 w/0 GDi NAT U

TURKEY POINT 3,CYCLE 11 IFjA TURKEY POINT 4, CYCLE 12

. IFBA ST, LUCIE 2, CYCLE 5 8'w/o GD, NAT U

Go203-U02 OFFERS TWO MAJOR ADVANTAGES UVER BqC-01203 REDUCED AVERAGE LHGR

-.FUEL RODS OPERATED FURTHER FROM DNB AND LHGR LIMITS INCREASED URANIUM LOADING ALLOWS LOWER ASSEMBLY AVERAGE ENRICHMENTS, THUS LOWER FUEL CYCLE COST

Enclosure 4

ST, LUCIE UNIT 2 CYCLE 3 LTA PROGRAM DESCRIPTION

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FUEL ROD DESIGNS FOR THE GADOI.INIABEARING I.EAD TEST ASSEMB I.IES UO2 FUEL ROD Gd203-UO2 FUEI. ROO UPPER ~

ENO CAP UPPER ~

END

.CAP SPRING SPACER FUEL PELLETS NATURAL UO2 6 Pit ACTIVE FUEL LENGTH 136.70" 32 WT%

UO2 124.7" SPRING SPACER FUEL PELl.ETS NATURAL UO 13$

'ATURAL UO2 WITH 8 WTYo Gd203 109.7" ACTIVE FUEL LENGTH 138.70" FUEL CLADDING FUEL CLADDING SPACER NATURAL

UO2 6 pt ~

SP AGER NATURAL UOZ 13.5" LOWER END CAP LOWER ENO CAP

LATTICE LOCATIONS FOR GDgO34l02 RODS 1N THE GADOL!NIABEARING LEAD TFST ASSEMBLIES Q UOE FUEL ROO LOCATION g GOEOE.UOE ROO LOCATION ONTROL ROD GU1DE TUBES

OO ST. LUCIE UNIT 2 CYCLE 3 CORE LOADING MAP, LEAD TEST GADOLINIAASSEMBI.Y PLACEMENT, AND INCOR E DETECTOR LOCATIONS NORTH C

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COMBUSTlON ENGINEERINQ EVALUATION METHODOLOGY FOR GADOUNIA-URANIARELOAD GORE DESIGNS

TABLE OF CONTENTS

$.0 INTRODUCTION 2.0 METHODOLMY o NEUY'RCNICS

- DIT CODE ROCS CODE

- MC Coal

" CR088 GEGTION TABLESEl8

- ROCSlMC MODELS

~ FUEL PERFORMANCE

- GADOLINIA-URANIAMATERIAL PROPERT1ES

- GADOLINIA-URANIAMODELS IN FATESG

- DATA COMPARISON 8.0 BENCHMARK ANALYSES ISOTOPIC ANALYSES

~ BSN t:RITICALS

< OQQNEE uNIT 1 LTA CORE FQLKlI'EMCHMARK8

+ ST. LUCIE UNIT 2 LTA CORE FOLLOYE BENCHMARKS 4.0 LICENSING APPLICATIONS

~ NEUTRONIC8 MODELING

+ FUEL PERFQRQANCE MODELING 6,0 CONCLUSIONS

SECTION 1. 0 INTRODUCTION OBJECT IVE:

TO OUTI INE REASONS FOR PREPARING A TOPICAL ON GAD AND OUTLINE MANUFACTURING PROCESSES KEY POINTS:

1, FPL AND OTHER C-E CUSTOMERS ARE INTERESTED IN GAD BECAUSE:

o GAD EXPED ITES LONGER CYCLES (AND MTC CONTROL FOR SANE),

o GAD CAN IMPROVE ECONOMICS (FEMER FUEL RODS DISPLACED),

o GAD CAN IMPROVE DNB AND LHR MARGINS (BY LOVlER AVG, LHR),

o UTILIZATION IS IMPROVED BY INCREASED EXPOSURE FOR A

GIVEN ENRICHMENT, 2,

GADOLIN IA-URANIA PELLET FABRICATION EMPLOYS:

o NATURAL U02 o. SAME 'DENSITY AND DENSIFICATION (X TD)

REQUIREMENTS AS U02 o

BLENDING OF U02 AND GD203 POMDERS SIMILAR TO U02 o

SAME GRAIN SIZE REQUIREMENT AS U02 o

RESTRICTED Go203 AND U02 FREE PARTICLE SIZE TO PROMOTE HOMOGENEITY

-0 ~--

ee SECTION 2,0 METHODOLOGY' NEUTRONICS

- DIT CODE:

SPECTRAL AND SPATIAL ASSEMBLY SPECTRUM CODE o

TRANSPORT THEORY, SPECTRUM CALCS IN 01 OR 85 GROUPS o

FEW GROUP CALCS IN EXACT ASSEMBLY GEOMETRY o

LEAKAGE CALCS TO MAINTAIN CRITICAL SPECTRUM o

ISOTOPIC DEPLETION FOR EVERY CELL; INCLUDING SUBREGIONS WHEN NECESSARY o

PRODUCES FEW-GROUP AVERAGED FINE-MESH AND COURSE-MESH CROSS-SECTIONS (FED TO ROCS a

MC)

-ROCS CODE:

COURSE MESH CORE SIMULATOR o

2 GROUP DIFFUSION THEORY 0

2 D

OR 3 D QUARTERp HALFi OR FULL CORE GEOMETRY o

0 NODES.PER ASSEMBLY o

20 TO 30-AXIAL NODES o

THERMAL HYDRAULIC FEEDBACK MODEL o

IMBEDDED LOCAL FLUX AND POWER DISTRIBUTION CALCS o

CALCULATES ISOTOPIC DISTRIBUTIONS o

CEA's REPRESENTED BY MACRO CROSS-SECTIONS FOR EACH BANK o

DEPLETION MODULE (INCLUDING XENON) o CRITICALITY SEARCHES (INCLUDING POWER

LEVEL, CEA BANK INSERTION, SOLUABLE BORON AND. MODERATOR TEMP)

-MC CODE:

IMBEDDED, FINE MESH ASSEMBLY CALCULATOR o

RETRIEVES LOCAL FLUX AND POWER DISTRIBUTIONS FROM ROCS o

USES MACRO CROSS-SECTION FROM DIT o

PRODUCES EQUI VALENT OF FINE MESH POWER DISTRIBUTIONS

SECTION 2.0 METHODOLOGY o

FUEL PERFORMANCE-FATES CODE CALCULATES BURNUP AND SPATIALLY DEPENDENT FUEL ROD BEHAVIOR INCLUDING TEMPERATURE DISTRIBUTIONS, GAP CONDUCTIVITIES AND INTERNAL PRESSURES o

THERMAL EXPANSION MODEL o

RELOCATION MODEL o

CREEP MODEL o

SMELLING MODEL o

FISSION GAS RELEASE MODEL o

ELASTIC DEFORMATION MODEL

, o UP TO 20 DESCRETE AXIAL SEGMENTS o

DETAILED FUEL PIN REPRESENTATION

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SECTION 2.0 METHODOLOGY o

NEUTRONICS DIT CODE OBJECTIVE:

DESCRIBES DETAILS OF D IT MODELING OF GADOLINIA FUEL AND IDENTIFIES DIFFERENCES RELATIVE TO U02

MODELING, GAD MODELING FEATURES:

1, INCLUSION OF ALL GADOLINIUM CHAINS IN 01 AND 85 GROUP ENDF/B-IY LIBRARIES, 2,

USE OF 7 BROAD ENERGY GROUPS (4 THERMAL YS, 1),

3, USE OF AT LEAST 8 RADIAL SUBREGIONS IN FUEL PELLET REGION.

USE OF PREDICTOR-CORRECTOR METHOD TO,CALCULATE TIYiE STEP AVERAGED LOCAL FLUX SPECTRA AND CROSS SECTIQNS

{TO AVOID THE NEED FOR SMALL (50 MMD/T)

TIME STEPS),

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SECTION 2,0 - METHODOLOGY o

NEUTRONICS ROCS AND MC CODES OBJECTIVE; GAD MODELING FEATURES;

( IN ROCS)

DESCRIBES DETAILS OF ROCS AND MC MODELING OF GADOLINIUM FUEL AND IDENTIFIES DIFFERENCES RELATIVE TO U02 MODELING, 1.

REPRESENTATION OF 0

GADOLINIUM DEPLETION CHAIN ISOTOPES IN THE 2-GROUP, COARSE MESH MICRO CROSS SECTION

MODEL, 2,

FUNCTIONALIZATION OF GADOLINIUM CROSS SECTIONS TO ISOTOPIC NUMBER DENSITIES TO ACCURATELY ACCOUNT FOR SELF-SHIELDING, 3,

USE OF PREDICTOR-CORRECTOR TECHNIQUES AS IN

DIT, GAD MODELING FEATURES:

NONE, (IN MC)

MC CROSS. SECTIONS COME DIRECTLY FROM DIT.

SO USE OF GADOLINIUM IS DIRECTLY ACCOUNTED FOR,

SECTION 2,0 - METHODOLOGY 0

NEUTRON I CS CROSS SECTION TABLESETS OBJECTIVE; DESCRIBE IN DETAIL THE GROUP STRUCTURES, TINE STEP STRUCTURES AND

'EOMETRIES USED. IN MODELING GAD SPECIAL FEATURES FOR GAD:

1, INCLUSION OF ALL GADOLINIUM CHAINS, IN 41 AND 85 GROUP ENDF/B-IV LI BRA RIES,

.2, USE OF 7 BROAD ENERGY GROUPS (4

THERMAL VS, 1 NORMALLY).

USE OF AT LEAST-8 RADIAL SUBREGIONS IN FUEL PELLET REGION, 4.

ESSENTIALLY THE SAME TIME STEP STRUCTURE AS FOR ALL OTHER APPLICATIONS BUT MITH USE OF PREDICTOR-CORRECTOR METHOD TO CALCULATE TIME STEP AVERAGE FLUX

SPECTRA, 5,

INDEPENDENT CROSS SECTIONS FOR GAD AND U02 FOR EACH GAD LOADING FUNCTIONALIZED ON GAD AND DISSOLVED BORON NUMBER DENSITY AND MODERATOR TEMPERATURE,

SECTION 2.0 - METHODOLOGY o

NEUTRONICS

- ROCS/MC MODELS OBJECTIVE:

TO DESCRIBE THE ROCS/MC GEOMETRIES AND TIME STEP STRUCTURES USED IN MODELING GADOLINIUM FUEL SPECIAL FEATURES GAD:

1.

2 X 2 NODES PER ASSEMBLY WITH 20 TO 30 AXIAL NODES, 2,

1 MESH PER PIN CELL IN MC:

SAME AS FOR OTHER APPLICATIONS, DETAILED EDIT SETS FROM DIT TO MC.

EACH DIT EDIT SET DEFINES AN MC TABLESET TO GET ACCURATE FLUX DISTRIBUTION IN GAD POISON

RODS, CONVENTIONAL TIME STEPS

(+ 1000 MWD/MTU) EMPLOYED WITH THE PREDICTOR-CORRECTOR METHOD

SECTION 2.0 - NETHODOLOGY P

OBJECTIVE:

o FUEL PERFORNANCE DEFINE AND VERIFY FUEL PERFORMANCE NODELS FOR GADOLINIA BEARING FUEL KEY RESULTS:

1, INPORTANT PROPERTIES QUANTIFIED 2.

FUEL PERFORNANCE

CODE, FATES3i NOD I FIED 3,

BENCHNARKING OF CODE FOR GADOLINIA-URANIAFUEL CARRIED OUT

SECTION 2,0 - NETHODOLOGY o

FUEL PERFORNANCE GADOLINIA-URANIANATERIAL PROPERTIES OBJECTIVE:.

DEFINE INPORTANT NATERIAL PROPERTIES NEEDED TO ANALYZE GD203-U02 FUEL RODS KEY RESULTS:

1.

THERMAI CONDUCTIVITY AND SOLIDUS TENPERATURE ARE LOMER 2,

THERNAL CONDUCTIVITY CALCULATED FRON DATA ON DENSITY, SPECIFIC HEATi AND DIFFUSIVITY, I. E,,

K =

- ~

CP e

PROPERTY DATA AND RELATIONSHIPS COVER 0 TO 12 MT, X GD203 4,

FUNCTIONAL FORN OF PROPERTY RELATIONSHIP SANE AS FATES3 U02 PROPERTIES 5,

6, SCATTER BETMEEN DATA SOURCES ELININATED BY NORNALIZATION PROCESS DEFINED RELATIONSHIPS ARE BEST-ESTINATE

v ~

v SECTION 2.0 - METHODOLOGY o

FUEL PERFORMANCE GADOLINIA-URANIAMODELS IN FATES3 OBJECTIVE:

BUILD PROPERTIES INTO FATES3 FUEL PERFORMANCE CODE FOR PERFORMANCE ANALYSES KEY RESULTS:

1, PROPERTIES INCORPORATED 2,

BEST-ESTIMATE AND BIASED PROPERTY OPTIONS BUILT INTO FATES3 3.

PRELIMINARY BIASED PROPERTIES A. CONDUCTIVITY - 10'ONER B,

MELT TEMPERATURE - 180'C LONER

SECTION 2,0 - NETHODOLOGY o

FUEL PERFORNANCE DATA CONPARISONS OBJECTIVE:

ESTABLISH ADEQUACY OF THE FATES3 GADOL IN I A-URANIA NODEL KEY RESULTS; 1,

FOUR WELL-CHARACTERIZED U02 - 4WT, X

GD303 FUEL RODS RANPED IN STUDSVIK WERE NODELED 2.

BURNUPS WERE 32.5 vo 33.8 NWD/KGU, PEAK LINEAR HEAT RATES MERE 11,9 TO 15,4 KM/FT 3,

NEASURED FISSION GAS RELEASES WERE 10,8 TO 29,0X PREDICTED RELEASES MERE 18,0 TO 44. 1X (3 OVERPREDICTED, 1

UNDERPREDICTED) 5, MODEL ACCEPTABLY CONSERVATIVE FOR PERFORNANCE CALCULATIONS

SECTION 3.0 - BENCHMARK ANAlYSES

. 0 ISOTOPIC BENCHMARKING OBJECTIVE:

TO DEMONSTRATE MODELS ACCURATELY PREDICT ISOTOPIC DEPLETION RELATIVE TO MEASURED

DATA, RESULTS:

THE-CALCULATED-TO-MEASURED ISOTOPIC CONCENTRATION RATIOS AGREE WITHIN A FEW TENTHS OF A PERCENT FOR VARIOUS URANIUM, PLUTONIUM AND GADOLINIUM ISOTOPES,

SECTION 3.0 - BENCHMARK ANALYSIS o

BRW CRITICALS BENCHMARKING OBJECTIVE:

TO DEMONSTRATE MODELS ACCURATElY PREDICT MEASURED GAD WORTH AND ROD-BY-ROD POWER DISTRIBUTIONS RESULTS; 1,

PREDICTED WORTH OF THE GAD RODS WITHIN ABOUT +

. 1% DELTA RHO OF MEASUREMENT 2,

P INWISE POWER DISTRIBUTIONS WITHIN +

3',OF MEASUREMENT ABOUT SAME ACCURACY AS FOR NON-GAD-BEARING FUEL, 3,

THE RADIAL POWER DISTRIBUTION IN THE GAD TEST PINS MATCHES MEASUREMENT WITHIN + 3X,

1 2

3 4

5 6

7 8

1.277 1.267 1.110 1.105 17 1.082 1.059

'l.043 1.043 1.017 1.081 1.057 1.052 1,040 1.028 1.011 1,059

'L075 1.034 0,973 1.041

'1.056 1.067 1.030 0.996 0,168 1.238 1.268 1.073 0.164 0.161 1.223 1.252 1.062 0.159 1.284 0.972 1,231 1.011 1.280 1.045 1.243 1.030 1.077 0.962 1.059 0.979 1.010 1.023 0,979 1.001 0.954 0.981 0.999 0.993 0.999 0.999 0,978 0.969 CALCULATEDAND MEASURED POWER DISTRIBUTION FOR CRITICALWITH 32 GADOLINIUM-BEARING FUEL RODS CENTRAL 8 x 8 ARRAYAND MAINDIAGONAL 18 0.450 0.418 I

~2.'48 WT%

19 0.404 0.378 0.158 0.154 0.900 0.930 0.931 0.926 0.895

= 0.900 10 0.'I37'.135 0.875 0.850 12 13 0.298 0.273 0.240 0.227 0.206 0.195 25 4.02 WT' I

14 0.105 0.102

MEAS, CALC.

d203 UO2.

Water Hole 0.174 0.164 26 0.142 0.135 0.113 0.109 0.087 0.086 0.072 0.067 0.682 0.667 30 0,069 0.056 16 l

SECTION 3,0 - BENCHNARK ANALYSIS' OCONEE LTA BENCHNARKS OBJECTIVE:

TO DEYiONSTRATE MODELS ACCURATELY PREDICT NEASURED GADOLINIUN ROD BURNOUT RATES, GLOBAL POWER DISTRIBUTIONS AND DISSOLVED BORON RUNDOWN (REACTIVITY VARIATION),

RESULTS:

1, BURNUP DEPENDENT GLOBAL POWER DISTRIBUTIONS AGREE MELL:

ACCURACY ABOUT EQUAL TO NON-GAD-BEARING CORES (I,E,,

2 To 3X DIFFERENCES),

2, PREDICTED AND NEASVRED BORON RUNDOWN AGREE WITHIN ABOUT 35 PPN AT BOC AND 10 PPN AT EOC FOR 3 CYCLES:

ACCURACY ABOUT SANE AS NON-GAD-BEARING CORES, NEASURES LTA ASSENBLY BURNUPS AGREE MELL WITH PREDICTIONS:

CONPARABLE TO POWER DISTRIBUTION COMPARISONS,

OCONEE 1 CYCLE 8 RPD vs EFPD H08 TEST ASSEMBLY (CENTER) 1.20

~

PRED.ROCS (3D1 MEAS.

1.10 1.00 0.90 100 200 EFPD 300 400

SECTION 3,0 - BENCHNARKING ANALYSIS 0

ST.

LUCIE 2 LTA BENCHNARKS OBJECTIVE:

TO DENONSTRATE NODELS ACCURATELY PREDICT NEASURED GAD BURNOUT RATES, GLOBAI POWER DISTRIBUTIONS AND REACTIVITIES FOR C-E DESIGNED AND NANUFACTURED GADOLINIA-URANIA FUEL RESULTS:

DATA ANALYZED TO DATE IS EARLY IN CYCLE, LTA PERFORNANCE,TO DATE CLOSE TO PREDICTION, FINAL RESULTS TO BE AVAILABLE BY NARCH 31, 198$.

SECTION 4,0 LICENSING APPLICATIONS o

NEUTRON I CS OBJECTIVE:

DESCRIBE LICENSING NODELS THAT PROVIDE CONSERVATIVE GD203-U02 BEHAVIOR KEY RESULTS:

1.

STANDARD NEUTRONICS I'<ODELS 2,

SAFETY INPUT DATA GENERATION UNCHANGED 3,

CORRECTION FACTORS NEEDED FOR IN CORE DETECTOR CONSTANTS

SECTION 4,0 LICENSING APPLICATIONS o

FUEL PERFORMANCE OBJECTIVE:

DESCRIBE LICENSING MODELS NHICH DEMONSTRATE I'HAT 6020' U02FUEL RODS ARE LESS LIMITING THAN UO2 FUEL RODS FOR IMPORTANT FUEL PERFORMANCE PARAMETERS, KEY RESULTS:

1, IMPORTANT PERFORMANCE PARAMETERS ARE TEMPERATURES,

PRESSURE, AND CENTERLINE MELT 2I POWER PEAKS, TEMPERATURES AND FUEL ROD PRESSURES FOR THE LIMITING U02 ROD ARE MORE LIMITING THAN THOSE FOR THE LIMITING GD20g - U02 ROD FOR LTA'S,

SECTION 5,0 - CONCLUSIONS THE CONBUSTION ENGINEERING EVALUATION NETHODOLOGY FOR ASSESSING THE PERFORNANCE OF GADOLINIA-URANIA RODS PROVIDES A CONSERVATIVE PREDICTION OF EXPECTED

BEHAVIOR,

~

Enclosure 5

'D TOPICAL REVIEM SCHEDULE TO SUPPORT ST, LUCIE 2 CYCLE 5 SUBNIT TOPICAL TO NRC NRC TOPICAL APPROVAL PLACE UF6 ORDER UF6 WITHDRAWAL FUEL DELIVERY COMPLETED START REFUELIHG CYCLE 5 STARTUP ApR>c 1, 1987 DECENBER 31, 1987 MARCH 15, 1988 SEPTEMBER 23-30, 1988 NARCH 1, 1989 MARCH 16, 1989 NAY 18, 1989

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MEETING

SUMMARY

DISTRIBUTION PWR PROJECT DIRECTORATE ¹8

', Docket File

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NRC PDR L PDR PBD¹8 Rdg AThadani PKreutzer OELD EJordan BGrimes ACRS-10 NRC Partici ants RLobel DFieno CThomas ETourigny

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