ML20039G478

Forwards Core Performance Branch Second Round Questions Re PSAR for Facilities

ML20039G478
Person / Time
Site:	05000514, 05000515
Issue date:	04/25/1975
From:	Stello V Office of Nuclear Reactor Regulation
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 8201180292
Download: ML20039G478 (3)

Text

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0~100 DacLet tios.: 50-514 & 50-515 AFF. 2 5 i.il5 V. A. l'oore, Assistant Directcr for Light Water Reactors 2, RL SECOiD ROU::D QUESTI0 tis - PEBBLE SPRIriGS flUCLEAR PLAfiT, U:iITS 1 & 2 Plant !!ar.e:

Pebble Springs Docket I:os.:

50-514 & 50-515 Licensing Stege:

CP Eespcnsible Ercnch Lt.'P. 2-3 and Project Leader:

C. Stchle

~.id..:cd '.<_ ica Brt;.c;. Involved:

Fucis Section i. Fitysics Section Core N.rfcrmance h i.nch D:scription of Review:

Second I,cund Ot stions T w cr'.:d Cc aletion Date:

April 11, 1975

'.viu W.tus:

Complete The second round cuestions frem the R: actor Fuels Section and the Physics Section of the Core Performance Branch concerning the Pebble Springs PSAR are enclosed.

These questions relate to Chapters 4 (Sections 4.2 and 4.3) and 15 of the PSAR.

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V ctor Stello',/Jr., Assis ant Director s

for Reactor Safety Division of Technical Review Office of tiuclear Reactor Regulation

Enclosure:

Second Round Questions cc:

S. Hanauer F. Schroeder A. Giambusso W. ficDonald A. Schwencer D. F. Ross L. Rubenstein P. Check W. Brooks i

W. llodges 1

P. Atherton C. Stable R. Lobel L. Chandler I

e, g w m. p y

-h,,4 O/ 1M 6 B201180292 010403 PDR FOIA MADDEN 80-515 PDR

' 3-1

~ E41.0 F.EACTOR FUELS SECTIOf - CORE FERFOR"A!!CE ERANCH E41.8 In the rc ponte to question 241.6, it bas stated that the (t.2.1.3) frndicticn cro.;th of Zr-4 is a function of flucace. Give the specific values used by B&tf. l l e 1 l l

o. 240-1 2;2.0 RE/.; TOR TiiYSICS SECTIO - CORE PERFOR:%f;CE BRANCH e t i 142.27. l ', The response to the first part of question 242.5 was in-(4.3.2.2.2) adequate. Please explain, in detail, how offset limits are derived. Section 4.3.2.2.2 suggests that the offset i limits are defined by limiting power distributions and that limiting power distributions are power peaks which exceed i the design criteria relating to Dt:B or fuel centerline tel tir.p. L'e do not understand how p ::er distributions which cause design limits to be exceeded are used to describe an cn.tiope of accepitbie p0tter shapes. 242. 8 The response to the lest part of question 242.2' of the-(15.0) first vcund cuestions ves inedequate. Plette'c.xpirin ho. the uncertainties in the moderator temperature and Doppler cecificients are accounted for uhere these coefficients are c ployed in Chapter 15 accident and transient :nalyses. l 242.29 Analyze single rod withdrawal incident at both zero and l' (15.0) full power es an anticipated event, or show that it can not be caused by a single equipment failure or operator error. t i ? r k i e \\ \\ \\ r i l i i l } . -}}