ML19329C640

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Forwards SER Supporting Areas of FSAR of Primary Concern to Auxiliary & Power Conversion Sys Branch.Requests Addl Info for Items Incompletely Resolved in Amends to Fsar.W/O Encl
ML19329C640
Person / Time
Site: Davis Besse 
Issue date: 02/26/1975
From: Tedesco R
Office of Nuclear Reactor Regulation
To: Moore V
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8002180152
Download: ML19329C640 (2)


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Docket File NRR Reading pb 2 61975 CS Reading APCSB Reading Docket No.

50-346 Voss A. ". core, Assistant Director for Light h*atar Reactors, Group 2, L SAFF.TY EVALUATION P2? ORT Plant Name: Davis-Basse Nuclear Power Station, Unit 1 Licensing Stage: CL Docket Number: 50-346 Responsible Branch:

L'JR 2-3 Project Leader:

L. 3. Engle Raquested Cocpletion Date: February 7, 1975 (Approved copy forwarded to LTM 2/26/75)

The enclosed Safety Evaluatien Report covers the areas of the TSAR for which the Auxiliary and Pcvar Conversion Systems 3 ranch has primary responsibility.

Two formal requests for information were prepared and submitted to the applicant, the first dated July 25, 1973 and the second dated September 12, 1974.

'4e have reviewed various amendments, the latest Amendment Mo.

26 (Rev.11) which includes the applicant's answers to our formal requests for information.

Acendment No. 26 (Rev. 1) sud previous amendments responses do not fully co= ply with five of our requests. The areas which have not been completely resolved with the applicant are as follows:

(1) The divided surge tank e= ployed in the design of tha component cooling water system has not been provided with a seismic Cates;ory I secondary =akeup water supply (Paragraph 9.2.2)

(2) The URS heat dissipation canability la not adequata as presently 4

decigned (Paragraph 9.2.5)

(3) Assure the motor operated valvos installed in the auxiliary feedvater system satisfy power diversity by accessibility for manual operation in the event valve fails to operate, (Parar.rsph 9.2.7)

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Voss A. Mcore (4) Automatically operated upstream dampers are required in the fuel handling area emergency ventilation syste n (paragraph 9.4.2.2)

(5) The fuel oil storage and transfer system design for the standby diesel generators does not comply with IEEE-308 standards (paragraph 9.5.4)

With the exceptions noted above, we find the FSAR information acceptable in the stated areas.

Original signsd by Rccert G Teaesco Robert L. Tedesco, Assistant Director for Containment Safety Divisien of Technical Review Office of Nuclear Reactor Regulation

Enclosure:

As Stated cc:

S. Hanauer, TA F. Schrooder, TR A. Giambusso, RL W. Mcdonald, MIPC C. Long, APCSE A. Schwencer, RL L. Engle, RL S. Varga, RL D. Eisenhut, NRR D. Fischer, APCSB P. Matthews, APCS 3 A. Ungaro, APCSB J. Glynn, CS n

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