ML19319E064

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Summary of 790808 Meeting W/B&W Owners Re Current Progress & Projected Schedule for Completing Asymmetric LOCA Loads Evaluation
ML19319E064
Person / Time
Site: Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  Duke Energy icon.png
Issue date: 10/12/1979
From: Hosford S
Office of Nuclear Reactor Regulation
To: Shao L
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-02, REF-GTECI-EQ, TASK-A-02, TASK-A-2, TASK-OR NUDOCS 8003310561
Download: ML19319E064 (4)


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MEMORANDUM FOR: 6&rrp ec. HS hho paAc tin 6S A 55 t t t$n fi Dthecro f a r

-l f5cntn@i'nser4ng Programs Division of Op6Aat4ns4&ctors, THRU:

Vince Noonan, Chief

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Engineering Bianch Division of,0perating Readtors',

FROM:

Steven B. Hosford Task Manager (A-2)

Division of Opdrating Reactorsf,',

SUBJECT:

SumARY OF HEETING ON AUGUST 8,1979, WITH BABCOCX

'& WILCOX OWNERS T0' DISCUSS THE STATUS OF'THEIR ASY METRIC LOCA LOADS EVALUATION The staff met with the Babcock & Wilcox Owners on August 8,1979, to discuss their current progressMd' project'dd " schedule for cotoleting the Asynnetric LOCA Loads Evalustifon,. 4 'iumhar progress to 'date is provided 'iri]hejE,dcT,dsJr,e.{y 6f the B&W'0wner

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The B&W Owners informed the staff df a projected slip in their schedule.

The new schedule projects a slip [,of'apprdxii.ately 4 months, to July 1980.

The new schedule also excludes considefitio'n df the Steam Generator and Reactor Coolant Pump Cavity Losds Ana~ lysis, which was not rescheduled at this time.

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The staff informed the B&W Owners that a report providing a sufficient amount of the required analysis 'sh6did 'bd'cdmpleted and submitted, for each plant, in the required Januiffl980 'tfed frra The report on each

plant should provide'the staff 'with'idequate information to assess the safety significance of extending this 'schedd16'for'spproximately 4 months. The staff will~ provide further guidincd'od thd scope of this analysis, as
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8003310fg[ f Steven'B. Hosford, Tisk Manager (

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Enclosure:

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Enclosures:

1 Completed Work 2.

List of Attendees cc.w/ encl:

H. Denton E. Case D. Eisenhut F. Schroeder G. Grimes R. Vollmer W. Ga,-rtill J. ftiller J. Knight R. Tedesco V. floonan P. Check m

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LIST OF ATTTNDEES~

BABCOCK & WILCOX GROUP MEETING AUGUST 8, 1979 NBC S. Hosford-C. Ge Tinkler L. Shao t

i Babcock & Wilcox 1

D. L. Howell J. E. Galford

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J. K. Wood Florida Power Coro.

J.-V. Vastamattam Arkansas-Power & Licht D ARM

0. G.' Mardis obi Ouke Power Co.
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ASYMETRIC LOCA LOADS E'il.LUATION OVERVIEW 0F PROGRESS AilD COMPLETED WORK p

ANALYSES AND TECHNICAL DOCUMENTS

- BAU 1506

" ASYMMETRIC LOCA LOADS EVALUATION - PHASE 1"

- BAW 1538 "ASSUMPT10i!S, METHODOLOGY, AND ACCEPTANCE CRITERIA - PHASE 2"

- BAW 1517 "EFFECT OF HYDRODYl!AMIC MASS COUPLING ON THE TRANSIEi1T RESP 0iiSE OF REACTOR INTERilALS TO ASYMETRIC LOCA LOAD" 6

CAVITY PRESSURES

- MASS AND ENERGY CALCULATIONS FOR ALL PLANTS

- MODIFIED AND RECERTIFIED CRAFT CODE PER i4RC REQUEST (1.E, CHOKE CHECKS lil ALL FLOW PATHS -- MOODY DISCHARGE COEFFICIEili, CD = 0.6, APPLIED WHERE CHOKED FLOW OCCURS)

- CAVITY PRESSURE CALCULATI0i!S COMPLETED FOR TWO PLANT, REMAlllDER BY SEPTEMBER.

- EVALUATION OF FIVE SPECIFICKAVITY DESIGliS

0. INTERNALS PRESSURES.

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- REACTOR INTERNALS ASYMETRIC PRESSURES AND APs o [in e T g o f

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8 STRUCTURAL MODELING AI!D ANALYSIS

- REACTOR INTERNALS MODEL

- FUEL ASSEMBLY MODEL i

- REACTOR VESSEL SUPPORT EM3EDMENT SPRING RATES

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.- PIPE WHIP ANALYSES FOR TWO 0F SEVEN PLANTS - BREAK OPENitiG i

AREAS AND OPENING TI?iES

.8 SPECIAL TECHN CAL PRCGRAMS I

-- DEVELOPF.Ei;T 0F-HYDRODYi;AMIC MASS COU?LIi;E

- COMPARIS0ii STUDIES EETWEEN THE CODES CRACT AND C0"ARE