ML19319E295
| ML19319E295 | |
| 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 8004040587 | |
| Download: ML19319E295 (4) | |
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w t-DISTRIBUTION OCTOBER ~: 1373. Docket Files NRC PDR Local PDR SHosford a
D Generic Task A-2
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MEMORNiDUM FOR:. Ea rryeC. HS hho MAe ting c A s s t s ein t i Dt decro fa r fornEn@ineering Programs
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Division of Opebat5nyde&ctors, THRU:
Vince Noonan, Chief
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' Engineering Branch'
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Division of,0perating Readtors',
-l FROM:
Steven B. Hosford, Task Manager (A-2)
Division 'of Opdrating Reactorsf ~,
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SUBJECT:
SUW.ARY OF MEETING ON AUGUST 8,1979, WITH BABC0CV,
& NILC0X NNERS T0' DISCUSS THE STATUS OF THEIR
-ASYPRETRIC LOCA LOADS EVALUATION l
The staff met with the Babcock & Wilcox Owners on August 8,1979, to discuss their current progressa'n'd 'pirject'ed ' schedule for corsleting D
the Asymetric LOCA Loads Evaluit'fori." "A sur.ary 6f the B&W Owners progress :to date is provided ~irj 'th(EridT,6sure{ ~ ;
c The B&W Owners ' informed the staff df a projected slip in their schedule.
~ The ned schedule projects' a slifof ap;iroxii.ately 4 months, to July 1980.
The new schedule also ' excludes considefition df the Steam Generator and Reactor Coolant Pump Cavity Lodds Analysi,s,',; which was not rescheduled
- at this tice.
The staff informed the B&W Owners that a report providing a sufficient amountiof the. required analysis sho'uld bd 'cdmpleted and subaitted, for-each plant,Lin the required Januiry1930 time frem.
The report on each
. plant:should provide the staff with 'adeduate information to assess the safety significan::e.of extending thisIschedsid'for'spproximately '4 nonths. The
' staff will provide further guidined'ori ths scope of this analysis, as
_ reques te d by the B &W Osners. ' f,] ],~ ',,, ',,'; '
i StevenB.Hesford,TiskManager(A-2)-
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Division of Operating Reactors
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Enclosure:
See next page
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OCTOBER. 1 2 1373 c,
Enclosures:
il., ; Completed Work.
~ 2.2 : List of. Attendees
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. H._ Denton :
E. Case-0; Eisenhut-
.F.2Schroeder B.2 Grimes-R.; Vollmer k'. Gamill -
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LIST OF ATTINDEESi
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BABC0CX & WILC0X GROUP MEETING
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ASYIfiETRI C L LOCA T LOADS : EW.LUATI0f t
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4-OVERVIEW 10F: PROGRESS AilD COMPLETED WORK
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- 0 ANALYSESJAi!D; TECHNICAL-DOCUMENTS-
"BAU 1506. ="ASYifiETRIC-LOCA LOADS EVALUATION - PHASE 1"
- -BAWil538
."ASSUMPT10i!S, METHODOLOGY, AND ACCEPTAllCE CRITERIA
< PHASE 2"
- BAW 1517u "EFFECT OFjHYDRODYllAMIC MASS COUPLif!G' Oil THE TRAiiSIEiiT RESP 0.lSE OF REACTOR INTERi:ALS TO
- ASYliiETRIC LOCA LOAD" 1
0; CAVITY PRESSURES-
- MASS AI'D EllERGY. CALCULATI0i!S FOR ALL PLANTS
- MODIFIED:AI!D RECERTIFIED CRAFT CODE PER iiRC RE00EST
- (1.E, CHOKE CHECKS Ifi ALL FLOW PATHS -- MOODY DISCHARGE 3
COEFFICIEllT, Cn = 0,6, APPLIED WHERE' CHOKED FLOW OCCURS)
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CAVITY PRESSURE CALCULATIONS COMPLETED FOR TUO PLAi;T:
REMAlll DER BY SEPTEMSER.
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- EVALUATION!0F FIVE SPECIFIC KAVITY DESIG!iS IIF liiTER!?ALS. PRESSURES
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cREACTOR liiTERiiALS ' ASYMMETRIC PRESSURES Ai p e
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0 ; STRUCTURAL MODELII;G AND ANALYSIS Ll
-- REACTOR zlNTER.4ALS MODELS FUELTASSEMSLY'MODEL
- REACTOR (VESSEL 2SUP?0RT EMBEDMEiii SPRIfiG RATES J-PIPEbWHIPoA:ALYSES FOR TWO OF SEVEN PLANTS - BREAK OPEiili;G:
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8iSPECIALETECH)l1CALPROGRAMS
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