ML20039G549

Forwards Previously Submitted Question 214.9 Re PSAR for Facilities

ML20039G549
Person / Time
Site:	Davis Besse
Issue date:	12/23/1975
From:	Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Moore V Office of Nuclear Reactor Regulation
Shared Package
ML111090060	List: ML19208A315 ML19208A325 ML19250B014 ML19250B445 ML19250B480 ML19250B482 ML19254C975 ML19254G119 ML19254G128 ML19255K396 ML19255K397 ML19257E274 ML19257F047 ML19257F050 ML19260B823 ML19260E912 ML19260E913 ML19260E914 ML19261C469 ML19262E467 ML19262F230 ML19263D836 ML19263F605 ML19263G068 ML19268C086 ML19268C087 ML19269F130 ML19271A085 ML19271A172 ML19273B051 ML19273D308 ML19274A409 ML19274E085 ML19275B428 ML19275B444 ML19275C327 ML19275C328 ML19275G904 ML19275G918 ML19275H308 ML19275H317 ML19275H339 ML19275H341 ML19275H375 ML19275H401 ML19275H405 ML19275H493 ML19275H655 ML19275H660 ML19276D594 ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8201180407
Download: ML20039G549 (2)

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V. A. Moore, Assistaat Director for Light Water Ecactors Croup 2. EL STAFF FOSITION FOR DAVIS BESSE UNITS 2 & 3

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Plant Eames Davis Besse Units 2 & 3 i

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Docket 1kanbers 50-500 & 50-501 Mi1== tone Number 12-24 I

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Responsible Branch LEE 2-2 cad Project h=g-r:

1. Senedict Techafe=1 Review Branch Tmolveds Core Forfor==nem Branch l

Description of Reviews Staff Focition t.~ %

Requested Corplation Date Jan==ry 2,1976 )

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M The Core Perfor==nem 3rench has no further questions on the Davis Basse Units 2 & 3 PSAR. One previous question, 241.9 (attcched), has not been answered in Revision 4. March 1975, as e1=4=ad.

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Oris!nal SIgneRug Victor SteDd Tietor Stallo, Jr., Assistant Director for nametor Safety Division of Technical Review Office of Nuclear Reactor Eagalariam rac1aeores As stated.

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Distribution:

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. Central Files L,'

E. Boyd Reading File V. Erm11m B Reading File K. Ynfm1 B. Benedict D. Ross F. Check L. Rubenstafa r,'.1 -

W. McDonmid S. Yarga B.Boustan W. Brooks

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CPB:T1 CP3:T1 RS:AD D. Bouston L. Rubenstein W. Brooks P. Check D. Ross Y.Stello 12/

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8201180407 810403 PDR FOIA MADDEN 80-515 PDR

a ENCLOSURE 1 241.9 (4. 2.1. 2. 2)

Provide the deflection design specifications (including dimensions and spring constants) and experimental cbser,

vations for the upper and lower plenum springs. Is there evidence of pemanent deflection due to fuel rod and fuel assembly handling? Would gradual deflection of the lower spring be expected as a function of irradiation and what is the maximum deflection, both expected and possible?

Discuss the QC procedures which assure that the proper type of spring is in the lower plenum.

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