ML19329C351
| ML19329C351 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/09/1976 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| NUDOCS 8002130716 | |
| Download: ML19329C351 (3) | |
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Distributiort Docket File NRC PDR DEC 9 576 Local PDR LWR-1 File D. Vassallo J Stolz h.
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Docket '!o. 50-346 H. Smith Chairman, Advisory Comittee R. S. Boyd on Reactor Safeguards R. DeYoung U.S. Nuclear Regulatory Comission Washington, D.C.
20055 Gentleren:
ISSUAfiCE OF DAVIS-BESSE UNIT 1 SAFETY EVALUATION REPORT (SER)
Sixteen copies of the Safety Evaluation l'.eport (SER), prepared by the Office of "uclear Peactor Regulation in the matter of the application filed by the Toledo Edison Cocoany and the Cleveland Electric Illu-mating Company for a license to operate the Davis-Sesse 1:uclear Power Station, Unii: 1, are enclosed for review by the Comittee.
There are still sone outstanding issues to be resolved. These issues are identified in the enclosure. Ue hope to be able to discuss the resolution of a r.unber of these issues at the Subcomittee meetino and subsequent full Comittee meeting.
Sincerely, Orginal signed by D. B. Vassallo, Assistant Director for Ligh2 Mater Reactors Divisien of Project Panagement
Enclosures:
1.
Outstanding Issues 2.
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OUTSTANDING REVIEW ITEMS DAVIS-BESSE UNIT 1 (1) Acceptability of the second year of onsite r sterological data (Section 2.3.4)
(2) Analysis of reactor coolant system response to pressure tran-sients that can potentially occur during startup and shutdown (Section 5.2.2)
(3) Leakage Detection System (3ection 5.2.4)
(4) Performance of surveillance caosule specimen holder tube based on reactor internals virbration test assessment (Section 5.3)
(5) Analysis of the decay heat removal system relief capacity (Section 5.5.3)
(6)- Evaluation of the reactor cavity pressure response analysis (Section 6.2.1)
(7) Analysis for pressure response of the shield buildina following apostulatedloss-of-coolantaccident(Section6.2.3)
(8) Evaluation of emergency core cooling system performance con-sidering minimum containment pressure, submerged valves, effects of boron precipitation, and single failure criteria (Section 6.3.3)
(9) Review of door seals and control room pressure tests to verify control habitability (Section 6.4).
Applicant has been requested to provide additional information.
(10) Review of the safety related electrical logic and schematic diagrams and the vetifica;.f on of the implementation of the design (Section 7.1)
(11) Verification of the reactor pr;tecticn system equip'ent qualification testing (Section 7.2).
Applicant will submit results in December 1976'.
(12) Modification on redundant reactor coolang flow transmitters in order to meet single failure criteria (Section 7.2).
(13) Evaluation that inadvertent closure of the low pressure to high pressure valves will not preclude decay heat removal to cold shutdown (Section 7.3.4 and 5.5.3).
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n (14) Evaluation of the modified steam and feedwater line rupture control system (Section 7.4.1).
(15)
Evaluation of separation criteria for redundant safety related electrical cables in trays, wireways, and conduits (Section 7.4.2).
(16)
Evaluation of backup protection and short circuit interrupt tests for containment electrical penetrations (Section 7.10).
(17) Evaluation of the environmental qualification of safety related equipment in a postulated nain streamline break accident environ-ment (Section 7.7).
(18). Equipment failures due to degraded grid voltage drop (Section 8.2).
The applicant has provided information which the staff is presently evaluating.
(lo) Evaluation of the applicant's financial qualifications to operate the facility (Section 20.0).
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