ML19319D435

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Forwards Second Round Request for Addl Info Re Auxiliary & Power Conversion Sys.Present Decay Heat Removal Sys Design Inadequate
ML19319D435
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/05/1973
From: Tedesco R
US ATOMIC ENERGY COMMISSION (AEC)
To: Deyoung R
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19319D436 List:
References
NUDOCS 8003170567
Download: ML19319D435 (2)


Text

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a" si t, Q > ?. c_ i s_ p. 'g, ,f. = ~ ' ' * ^ - _. [. s w, n a n. ,b. [ L k,. Om "~. a Docket No. 56302c Richard C. DeYoungi Assistant Director for Pressurized Water Reactors, L f AUXILIARY AND POWER CONVERSION' SYSTEMS BRANCE.EEQUEST-TOR ADDITIONAL IEFOWATION FOR CUTE RIVER NUCLEA% GrynATING FLANT,. UNIT 3 ' _ 7 _ y .[, y.. , R: n.. Plant Names q rystal River Nuclear Generating Plant, Unit'3 C Licensing Stage: OL Docket Number:-~50-302;'~, 2 aspen 21ble Drench: PWR-4 Rasponsibla Project'Leadertl ~B. CO3uckley Requested Completica Datas; May lb,.1973 Applicant's Response! QulyS13;'1973 Review Status: ' Completed second-round request for additional infor=ation - The saclosod:sccend-round rsquest for. additional inforirstica for ths operating liccuse ravicv of tha Crystal River liuclear Ger.wratQ1g ?lsat, Unit 3,.has. baan prepared by.the A m ary and Power Convarsion Systena Branch after having reviwedithe ep11 cable portions of the FSAR where ve have primary responsibility for review and. th respcases to requests previously subnitted to the applicent via the first-round quastion lint generated by the project u.an3Eer's raview, 'Accordingly, tha attached request represents the AFCS Branch first-round review of tha facility. Based en our' review of tha applicant's-design'of the-decay heat removal ~ system, we hava concluded that the present, design does not provide for au acceptably lw prol.obility for the inadvertant high pressurizatien' of the low dasign pressure syntaa...It is ur position that tw valveo should be provided with.a highly reliable control system to assure thatLthey will alosa ^ automatically whenever. the pressurs -in the primary coolant systez ' t exceeds tha ' low ' pressure systera martman operating pressure. _ The control - f system's interlocks:should be in-accordance:rith the criteria set by, ths WWEsotrical an(Instr====*= tion. Control Systems 3 ranch. ' 'i, R$f g w . : -n O. nxme L y s .n ' . ~. %.. r:4. wp s. . n ~ -' v a. ,e, - - e '\\d ' [ ' s.h.. LDA e ' = d ' b y - -.e s ,.e ~. .s. I ,O

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- C, @,. '.. ~ ' - :w g- , '~ c. L:CS ~ .~ ~ JUN 5 E:L APCSE ~~ Richard C. DeYoung The acceptability of the design End' any additional information relating ~ to the pitimate haat sink and plant flood protectica capabilities will be dependent upor the final results of the applicant's nodal for the Probable Maxieum Hurricane, the Site Analysis Branch (hydrology) receipt of outstanding information, and a site visit achedulad for the last half of July. One area where difficulty may ba ancountered during the review and will require a aseting with ths' applicant, relates to the acceptability of the design of the nuclear services cooling water system and the nuclear servica elesed cycle cooling water system with respect to its capabilities to withstand the effects of a single active or fassive failure so that long tarned post-accident cooling will be assured. ~ Robert L. Tedesco, Assistant Director for Con:nics,mt Safaty Directorate of Licensing Encionure: As stateri g cc: (w/o encl.) A. Giar.busso W. Mcdonald (w/ encl.) S. Hanauer J. M. Hendrie A. Schwencer- . f ~ ~ ' -Y; #k ' 7M k

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