ML19329B679

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Forwards Electrical,Instrumentation & Control Sys Branch Input Suppl to Facility Ser.Open Items Remain
ML19329B679
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/28/1976
From: Tedesco R
Office of Nuclear Reactor Regulation
To: Vassallo D
Office of Nuclear Reactor Regulation
Shared Package
ML19329B680 List:
References
NUDOCS 8002060687
Download: ML19329B679 (2)


Text

_

CEO28 56 Cocket No. 50-346

!!Ef10RAllDU'i FOR:

Dcmenic 3. Vassallo. Assistant Director for Light Water Reactors, CPM FROM:

Robert L. Tedesco, Assistant Director for Plant Systems, CSS

SUBJECT:

CAVIS BESSE Uti1T 1 SAFETY EVALUATION REPORT SUPPLEMENT Plant Name:

Davis Besse Unit 1 Docket Number:

50-346 Licensing Stage:

CL Milestone l'urcer:

27-22 Responsible Branch L'.!R 2 and Project Manager:

L. Engle Requested Completion Date:

Decetter 15, 1975 The DSS:PS, Electrical, Instrumentatien and Control Systems Branch input to the Davis Besse Unit 1 Safety Evaluation I!eport (SER) was transnitted by memorandun to you on dune ?3,1975. That input was based on a review of the FSAR through Amendment 28. Subsecuent trans-mittals to you dated Hovember 10,1975, June 17,1976, :iover.ber 4. Ic75, and Novecher 11, 1976, provided updated information for the Davis Eesse Unit 1 Safety Evaluation Report based upon information provided through Amendment 32 and our site visit. Sey?ral itecs in these trans-mittals were identified as subjects to be addressed in the SER Supplenent.

The supplementary report transmitted herewith addresses these items and presents the results of our review through AT.endoent 39 and in part, Amendment 40 (which was received Dettember 3,1976).

It should be noted that some, but not all, of the itens identified inthe previous trans-mittals have been resolved. The following iters are these that have not been satisfactorily resolved and recain as outstanding items. We will report our evaluation of these open itens in a supplement to this report.

1.

Final Approval of Er.vironmental Equipment Qualificaticn (SSER Section 7.9) Resolution is subject to satisfactory ccepletion of the Main Steam Line Dreak. Accident Analysis (SER Section 6.2) yet to be submitted for review.

2.

Final Approval of Class lE Isolation and Separation Systems.

Resolution subject to verification tests conducted by the applicant O36 demonstrating adequate isolation and separation between safety and Af -/

non-safety systems and desi em modifications fcr reacter coolant flow transmitters

[SSER Section 7.2). We are awaiting applicant's

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DEC 2 81976 Domenic B. Vassallo 2

3.

Final approval of the Decay Heat Removal Valve System (SSER Section 7.3.4) Resolution subject to concurrence from RSB.

4 Final Approval of the Applicant's Separation Criteria (SSER Section 7.9.2 and 7 9.3) Resolution subject to verification tests yet to t* submitted by the applicant and completion of our review of recently submitted infomation.

Ori%nal Sirv d by Itchert L. L' Jesco Robert L. Tedesco. Assistant Director for Plant Systems Division of Systers Safety

Enclosure:

As Stated cc:

S. Hanauer R. Heineman R. Coyd W. FcDonald T. Ippolito J. Stolz L. Engle C

iiller D. Tondi M. Srinivasan A. Ungaro J. f'azetis A. 5:ukiewicz BIIIIRBM DISTRIBUTION tdCKETFILE NRR READING FILE PS READING FILE EIC READING FILE R. L. TEDESCO A

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