ML19319E064
| ML19319E064 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane |
| 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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l OCTOBER **DS Docket FileV I-NRC'PUR '
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Generic Task A-2 Docket Nos 50-313 D
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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:
See next pace Division of' Operating Reactors j,
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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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-W. R. Speight TECo s
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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R. L.-Gill i
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i R. A..Dieterich Met. Ed.
R. A.- Langel GPU Service Corp.
L. Lanese
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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