ML19329B036
| ML19329B036 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/29/1972 |
| From: | Sampson G TOLEDO EDISON CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001290748 | |
| Download: ML19329B036 (2) | |
Text
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AEC D#~B GUTION FOR PART 50 DOCXET MI ~ RIAL (TEMPORARf FORM)
CONTROL NO: 09
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DATE OF DOC:
DATE REC'D i LTR IGMO RP2 (7IER Toledo Edison Co=pany Toledo, Ohio' 43652 Glenn J. Earpson 12-29-72 1-3-73 X
TO:
ORIG CC (TidER SE?i2 AEC FD3 x
SEN2 LOCAL PDR x
Mr. Gianbusso 1
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1 50-3h6 DESCRIP2 ION:
ENCLOSURES:
Ltr re our 12-15-72 ltr...... furnishin6 info regarding rupture of the min steam & feedvator piping outside of the containment,relatin6 to "i
ir'J the Drri -Besse Nucle?.; Power Station.......
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Gaw J. SaupscN C,
fra%g v.c. p,, a.et Power W
Dece=ber 29, 1972
'N Mr. A. Gia=busso, e'
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Deputy Director for Reactor Projects Directorate of Licensing tj.ygf V
U.S. Atc=ic F.nergy Cc==ission
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Docket No. 50-3h6 i
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Dear Mr. Gia=busso:
22, 1972. *!Ii,, p,
O, Your letter of Dece=ber 15, 1972, was received on Dece=ter Criterien No. k of the Cen=ission's General Design Criteria listed in Appendix A cf 10 CFR Part 50 has been cc= plied with in the design of the Davis-Besse Huelear Pcwer Station, including protection against the dyns=ic effects of pipe whipping and discharging of fluids associated with a rupture of the =ain steam and feedvater piping cutside of the contain=ent.
The =ain steam lines do pass thrcugh the upper level of the auxiliary building above the centrol rec =, hcvever, these lines are restrained to prevent whipping resulting frc= any type of postulated break and the rcof design of the ec=part=ents through which these lines pass are de-signed to vent the energy release resulting frc= a pcstulated rupture without unacceptable damage to the building structures or critical equip =ent.
The feedvater lines pass through the auxiliary buildings at lover elevations and are similarly restrained to prevent whipping frc= any postulated break.
Section 3.6, entitled " Criteria for Protection Against Dyna =ic Effects Associated '41th a Less-Of-Coolant Accident," of the FSAR for the Davis-Eesse Station prepared to Standard Format and Centent of Saf' z-Analysis Reports for Nuclear Pcver Plants, issued February 1972, centains criteria generally applicable to the =ain stea= and feedvater syste=s. Revisien 1, issued Ceteber 1972, of the Standard For=at calls for a description of the design bases and design ceasures for all piping subject to dynamic effects associated with a postulated rupture and the FSAR is being revised acecrd-ingly. This revisien vill also take into account the guidance centained in the general information request enciesed in ycur letter.
This revision is expected to be ec=pleted within 60 days of this date.
Yours very truly, k
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300 MADISCN AVisuE TOLECC. CHIO 43652 GJS:cd
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