ML20091S443
| ML20091S443 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/31/1992 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091S444 | List: |
| References | |
| NUDOCS 9202060424 | |
| Download: ML20091S443 (5) | |
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TOLEDO EDISON COMPAllY CENTERIOR SERVICE COMPANY AND THECLEVELANDELECTRICILLUMINATINGCOMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 A!1EN0!1ENT TO FACILITY OPERATING LICENSE Amendment No.169 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Compan Company (the licensees) y, and the Cleveland Electric illuminating dated May 10, 1991 and supplemented December 21, 1991, complies with the standards and requirerents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules ano regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
9202060424 920131 PDR ADOCK 05000346 P
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(6) Technical Specifications The Technical Specificatier.s contained in Appendix A, as revised through Anendment No.169, are hereby incorporated in the license.
The Toledo Edison Comp *.ny shall operate the f acility in accordance with the Technical Specifications.
3.
This license amendment is ef fective as of its date of issuance and shall be implemented not later than 45 days after issuance.
FOR THE NUCLEAR REGULATOR': COMMISSION JW
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on B. Hopkins, Sr. Project Manager
- Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Attachmer,t: Changes to the Technical Specifications Date of issuance: January 31, 1992 l
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l ATTACHMEtlT TO LICENSE AMENDMENT NO 169 FAC1: ITY OPERATitlG LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number ard cor.tain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 6-5 6-5 6-6 6-6 5
ADMINISTRATIVE CONTROLS
- 6. 3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the.'ianager - Radiological Control who shall meet nr exceed the qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents, and (3) the Manager - Plant Operations whose requirement for a senior reactor operator license is as stated in Specification 6.2.2.g.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Manager - Nuclear Training and shall meet or extted the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and of 10 CFR 55.59.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction-of the Manager - Nuclear Training.
- 6. 5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)
FUNCTION 6.5.1.1 The' Station Review Board (SRB) shall function to advise the Plant Manager on.all matters related to nuclear safety.
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DAVIS-BESSE, UNIT 1 6-5 Amendment No.
,29,9E,J06,135.J3E,
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ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The Station Review Board (SRB) shall be composed of at least six members of the Davis-Besse onsite management organization.
The members shall be as a minimum, managers or individuals reporting directly to managers from each of the following disciplines:
plant operations, maintenance, planning, radiological controls, engineering, and quality assurance. The members shall meet the requirements of ANSI N18.1-1971, Sections 4.2, 4.4, or 4.6 for applicable required experience.
The SRB Chairman shall be drawn from the SRB members and designated in writing by the Plant Manager.
ALTERNATES I
l E.5.1.3 All alternate members shall be appointed in writing by the SRB l
Chairman; however, no more than two alternates shall participate as voting j
members in SRB activities at any one time.
MEETING FREQUENCY 6.5.1.4 The SRB shall meet at least once per calendar month and as convened by the SRB Chairman or his designee.
I QUORUM
- 6. 5.1. 5 A quorum of the SPd shall consist of the Chairman or his desionee and _four members including alternates.
!! RESPONSIBILITIES 6.5.1.6' The Station Review Board sha 1 be responsible for:
a.
Review of plant administrative procedures and changes thereto.
b.
Review of the safety evaluation for 1) procedures, 2) changes to procedures, equipment or systems, and 3) tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question.
c.
Review of proposed procedures and changes to procedures and-equipment determined to involve an unreviewed safety question as defined in 10 CFR 50.59.
DAVIS-BESSE, UNIT 1 6-6 Amendment No. 12,76,98,J09,J3E,J29, J A2,169
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