ML19329B411
| ML19329B411 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/17/1976 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19329B412 | List: |
| References | |
| NUDOCS 8002050619 | |
| Download: ML19329B411 (2) | |
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Docket No.t50-346 R. C. DeYoung, Assistant Director for Light Water Reactors, DPH DAVIS BESSE UNIT NISfBER 1 SAFE'lY EVALUATION REPORT SUPPLDENT Plant Name:
Davis Besse Unit Number 1 Licensing Stage:
OL Docket Number:
S0-346 Ililestone Number:
27-22 Responsible Branen LWR 3 and Project Leader:
L. Engle Systems Safety Review Branch Involved:
EISCS Sranch Description of Review:
Safety Evaluation Report Supplement Requested Completion Date:
June 4, 1976 Review Status:
Complete with the exception of items stated in the Safety Evaluation Report and the Supplement Safety Evaluation Report The PS: DSS, Electrical, Instrunentation, and Control Systems Branch input to the Davis Sesse Unit Nunber 1 Safety Evaluation Report (SER) was trans,nitted to you on June 23, 197S. That SER was based on a review of the FSAR through Amendment 28.
A subsequent transmittal to you on November 10, 1975, provided updated infor=ation for the Davis Besse Unit Nuder 1 SER based upon infor:aation provided through Acendment 31.
This transmittal supplea:ents the information for the Davis Besse Unit Number 1 SER based upon information provided through Amendment 32 and should be inserted into the EICSB Safety Evaluation Report. It should be pointed out that some, but not all, of the items identified in the original SER have been resolved. The following items are those that have not been satisfactorily resolved and remain as outstanding items:
1.
Final approval of BAW-10003 Topical Report for the RPS equipment qualification Test Program. (SER Section 7.2).
Two items remain open (a) Reactor Coolant Pump Trip monitors response time veri-fication and (b) periodic testing of Reector Coolant Pressuro Motorola Transmitters.
We anticipate resolution of these items in the next====dment to the FSAR.
2.
Final approval of the Steam and Feedwater Rupture Control System renn w. p. v g _
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standing itens and cuantitted to provide modified design which would be' icc@ cable ~ttrthe~ staff.
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Final approval of the Cable Separation and Identificatica Criteria (SER Section 7.9).
4.
Documentation describing the degree of protection used for maintaining electrical penetration integrity (SER Section 7.10).
In a meeting held in Bothesda on May 26, 1976, the applicant agreed to amend the FSAR and to include the information requested by the staff.
S.
Completion of the drawing review.
It is anticipated that completion of this ites will be in July. We are seneduling two more drawing review sessions. One in June to review tne ESFAS and one in July to review the RPS systeu.
6.
Completion of the Site Visit. We anticipate completion of this item in July.
We will report resolution of these 1 cms in a suppletent to this report.
DISTRIBLITION DOCKET FILES NRR READING EIC READING PS READING Robert L. Tedesco, Assistant Director R. TEDESCO for Plant Systems Division of Syste=s Safety
Enclosure:
As stated cc:
S. Hanauer R. iieineman R. Boyd K. Kniel L. Engle T. Ippolito C. Itiller D. Tondi M. Srinivasan A. S:ukiewicz W. Mcdonald J. Glynn C-r iw EiCSB:PS CSB:PS EICS : S
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