ML20248E274

Amend 138 to License NPF-3,revising Tech Specs to Reflect Changes in Organization,Positions & Titles

ML20248E274
Person / Time
Site:	Davis Besse
Issue date:	09/20/1989
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248E276	List: ML20248E274 ML20248E277
References
NUDOCS 8910050127
Download: ML20248E274 (7)

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1. o UNITED STATES 8

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NUCLEAR REGULATORY COMMISSION c

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TOLEDO EDISON COMPANY AND THE CLEVFLAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.138 License No. NPF-3 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated March 8, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and 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 Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission'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:

8910050127 890920 PDR ADOCK 05000346

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.,2 (a) Technical Specifications

~The Technical Specifications contained in Appendix A, as revised through Amendment No.138, are hereby incorporated in the literse.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented not later than 45 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W

ohn N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 20, 1989

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g ATTACHMENT TO LICENSE AMENDMENT NO.

138 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 l

Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert l.

6-5 6-5 i.

6-6 6-6 6-9 6-9 l'

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ADMINISTRATIVE CONTROLS I

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 Radiological Controls Superintendent who shall meet or exceed the_

l qualifications of Regulatory Guide 1.8, September.1975 and (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 analysir, of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Director and shall meet or exceed 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 Nucicer Training Director.

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.

DAVIS-BESSE, UNIT 1 6-5 Amendment No. p.37,5),pS JP6,N M 138

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h-y COMPOSITION 6.5.1.2 The Station Review Board shall be composed of the:

Chairman:

Station Review Board Chairman

• l Member:

Assistant Plant Manager, Operations Member:

Assistant Plant Manager, Maintenance Member:

Technical Support Manager Member:

Radiological Controls Superintendent l

Member:

Operations Engineering Supervisor (Plant)

Member:

An Engineering Director Member:

Engineering Assurance Supervisor Member:

Operations Superintendent (Plant)

• Designated in writing by the Plant Manager. The Chairman will be drawn from SRB members.

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SRB Chairman; however, no more than two alternates shall participate as voting l

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members in SRB activities at any one time, k

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 designated alternate.

QUORUM 6.5.1.5 A quorum of the SRB shall consist of the Chairman or his desig-nated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The Station Review Board shall 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.

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a DAVIS-BESSE, UNIT 1 6-6 Amendment No. gN,95, /1A9,

,ADM]NISTRATIVE CONTROLS

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'V COMPOSITION 6.5.R.2 CNRB shall consist of a Chairman and four or more other members appointed by the Vice President. Nuclear.

No more than a minority of the

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members of the CNRB shall have line responsibility for the operation of the facility.

The CNRB members shall hold a Bachelor's decree in an engineering or physical science or eouivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.1.a through 6.5.2.1.h.

In the aggregate. the membership of the comittee shall provide specific practical experience in the majority of the disciplines of 6.5.P 3.a through 6.5.2.1.h.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNRB Chaiman; however, no more than two alternates shall participate as voting members in CNRB activities at any one time.

CONSULTANTS

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6.5.2.4 ' Consultants shall be utilized as determined by the CNRB Chairman to provide expert advice to the CNRB.

MEETING FREQUENCY 6.5.2.5 The CNRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

OVORUM 6.5.2.6 A quorum of CNRB shall consist of the Chaiman or his designated alternate and at least half of the appointed CNRB members or their alternates.

No more than a minority of the cuorum shall have line responsibility for operation of the facility.

f DAVIS-BESSE UNIT 1 6-9 Amendment No. J2. 77. 76. M. M.138

ADMIN!STRATIVE CONTROLS REVIEW 6.5.2.7 The Company Nuclear Review Board shall review:

a.

The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

Proposedchangest$ procedures,equipmentorsystemswhich involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59,10 CFR.

d.

Proposed changes in TulMcal Specifications or this Operating License.

e.

Violations of codes, tQu14tiens, orders. Technical Specifications, license requirements, or of internal procedures or instru:tions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from nomal and expected performance of plant equipment that affect nuclear.

safety.

9-ALL REPORTABLE EVENTS.

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All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures.

systems, or components.

1.

Reports and meetings minutes of the Station Revibw Board.

DAVIS-BESSE UNIT 1 6-10 Amendment No. 93 N +

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