ML19319D554

Forwards Request for Addl Info Re Steam Line break- Containment Pressure Analysis & Reactor Bldg Sump Screen

ML19319D554
Person / Time
Site:	Crystal River
Issue date:	05/22/1973
From:	Tedesco R US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8003170676
Download: ML19319D554 (3)

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EEQUEST HIR AUDITICHtd, INFOU:ATIG3 POR CRYSTAL.RIC, UNIT 3 Plant Kam: Crystal F.iver, Unit 3 t

Licensing StagcL OL' 7 ender: - Babcock and Milcox i

Architect Zagineer:. Gilbert Containments DrywPressure. coattatnr. ant Deckat Neder: <50-302 Responsible Branch:1 TW114 :

' Project Managart' 5. Buckley Requestod-Completion Date: May:18. 1973

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Applicant's 74cponse' Date: June 18, 1973-Deceription of Response: Pequest for Additicust inforuation

&;1cv Stat.c:.s: A Aiting Informatia:t I,

• Tha enclosed Esqucat for Additional Infor:sation-for the Crystal River, Unic 3 operatio; license revim.r has been prepared by t!ia Centaincent Eystero Seanch after having reviewed the.vplic.ible porths of the TSAR.

Othar qsmationa coverhk thA rajor arcan vere prgared on April 20, l'G3 ia acvance of tha 4 13, 15:13 requested co r;1ation data.

The enclosed qc:sticr.: inclw.ls rr.aunsts fcr.idditioni infonathn relat*d ts the =v>m 1?M hreak-rentainr.*ct 7tenna.wdy= f r, ;md the

. need for a descriptica cf the rasctar building sump ecreen,'

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i REQUEST FOR ADDITIONAL INFORMATION CRYSTAL RIVER, UNIT 3 DOCKET No. 50-302 1.

Provide the analysis of a split of a reactor coolant (5.2.6) pipe equivalent to a single-ended pipe rupture inside the biological shielding.

Include a discussion of the codel and assumptions used and a flow diagram showing all flow interconnections, the free volume and vent areas i

considered.

Compare the peak calculated pressure differ-

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ential in the pipe annulus to the design pressure differential.

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l 2.

Describe the protective sump screen assembly that will (6 * ~9~~'1) 9 prevent debris capable of clogging the containnent spray nozcles frca entering the surp suction piping.

Provide

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assurance that failure of a portion of the assembly will I

j not negate the effectiveness of the entire assembly.

Provide a drawing showing the physical arrangement of the l

assembly within the sump.

3.

Discuss the design provisions which permit the spray water (6.2.2.1)

.that may enter the refueling cavity and the reactor cavity following a loss-of-coolant accident to be drained to i

I the containment sump.

i Describe provisions made in the reactor building emergency (6.3.2) cooling system fans and ductwork to assure that the syste=

can withstand,.without loss of function, the differential i

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pressures imposed under the loss-of-coolant accident peak t '

containment pressure conditions.

t 5.

Discuss the potential additional increase in containcent pressure (14.2.2.1.5) following a steam line failure resulting from an increase in the feedvater flow.to the affected steam generators 4

(see Table 14-19).

Provide a single active failure analysis i

1 of both the feedwater and the energency feedwater systems which would result in additional flow to the affected steam generator.

6.

Provide a description of the calculations utilized to deterr.ine (14.2.2.1.5) the reactor building pressure response from the data supplied in Table 14-19, to a stean line rupture.

7.

Provide a description of how segment number 2 in the heat

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(14.2.2.5.5) sink-Table 14-41 was modeled for the reactor building pressure 6

analysis.

Provide a simplified diagram showing the relation-e

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i ship of the caterials including overlap and surface areas.

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Justify the thermal conductivity of 26 Btu /hr ft' 'F/ft (14.2.2.5.5) utilized for stainless steel, see Table 14-41 (thermal Y

properties).

A thermal conductivity for stainless steel less I

~ than half this value is usually the accepted value.

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9.

Resolve the following table and figure inconsistencies.

Table

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~ (14. 2.'2. 5. 6) 14-46 incorrectly references Figure 14-64.

Figure 14-20 i

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contains=a six-up in points A and 3.

The = ass rates in Figure

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14-64' are in error by a factor of.10.

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