ML20100F877
| ML20100F877 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/05/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100F874 | List: |
| References | |
| NUDOCS 8412070064 | |
| Download: ML20100F877 (2) | |
Text
.
- [
$(,
UNITED STATES p,
NUCLEAR REGULATORY COMMISSION.
r, j
wasmuovow. o. c.20sss
\\..../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.76 TO FACILITY OPERATING LICENSE NO. NPF-3 1
TOLEDO EDISON COMPANY 4
AND l
THE CLEVELAND ELECTRIC ILLUMINATING CC.!PANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1
' DOCKET NO. 50-346 i
4 INTRODUCTION 3
By letters dated December 26, 1980 (Item 5) and July 10, 1981, which were 4
l superseded by lettei of July 8,1983, Toledo Edison Company (the licensee) made application to amend Facility Operating License No. NPF-3 for the i
Davis-Besse Nuclear Power Station, Unit No.1, to reflect changes that were made
)
in names and titles of both the Company Nuclear Review Board (CNRB) and the i
Station Review Board (SRB) membership requirements, the relocation of some i
groups from the site organization to the corporate organization, and the deletion of licensed designations from positions in the SRB.
l EVALUATION The staff has reviewed the proposed changes and find that management control l
and lines of authority and communication have not been weakened by the proposed changes in the off-site or on-site structures and the QA organization has retained the safe independence and authority as is in the i
current Technical Specifications. We find that the station superintendent i
authority has not been weakened or diffused by the proposed on-site structure I
changes. The deletion of the operator license designations from positions in the on-site operating organization from Figure 6.6-2 does not relieve the
~
licensee from these requirements of ANSI NI8.1-1971, Selection and Training of i
Nuclear Power Plant Personnel for operations Management (Section 4.4.2),
Intermediate and First Line Supervisors (Section 4.3.1) and Operators (Section 5.4.1).
Based on the staft's review, the proposed Technical Specification changes are acceptable.
ENVIRONMENTAL CONSIDERATION i
This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or_ environmental assessment need be prepared in connection with the issuance of this amendment.
l 8412070064 841105 PDR ADOCK 05000346 P
~.
. J
e.
<' CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common 4
defense and security or to the health and safety of the public.
Dated:
November 5,1984 The following NRC personnel have contributed to this Safety Evaluation:
W. G. Rogers 6
i f
J 4
I
\\