ML20151X698

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Amend 112 to License DPR-51,deleting Tech Spec Figure 6.2-1, Mgt Organization Chart, (Offsite) & Figure 6.2-2, Functional Organization for Plant Operations
ML20151X698
Person / Time
Site: Arkansas Nuclear 
Issue date: 08/18/1988
From: Calvo J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151X703 List:
References
NUDOCS 8808260079
Download: ML20151X698 (8)


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UNITED STATES

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f,i NUCLE AR REGULATORY COMMISSION WASHINGTON, D. C. 20555 r,

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ARKANSAS POWER AND LIGHT COMPANY l

DOCKET NO. 50<313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 License No. DPR-51 1.

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

A.

The application for amendment by Arkansas Power and Light Company (the licensee) dated June 10, 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, as arended, 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 arendr.ent 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 license arendment 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 heen satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachrent to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.

DPR-51 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.112, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amende.ent is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION QG Jose A. Cal e, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 18, 1938 i

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i ATTACHMENT TO L1' TNT

<!ict 04T NO.112 FACILITY OPERA 1_n_'.

_'.<T_S. NO. DPR-51 DOCKET NO. 50-313 Revise 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.

REMOVE PAGES INSERT PAGES i

117 117 117a 117a 119 119 120 120 121 121 I

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Executive Director, ANO Site Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.

These relationships shall be i

documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the QA Manual Operations, i

b.

The Executive Director, ANO Site Operations, r+ hall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of i

the plant.

c.

The Vice President, Nuclear Operations, shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

FACILITY STAFF 6.2.2 The Operctions Superintendent and Shift Supervisor shall hold a senior reactor operator license.

The Plant Operators and Assistant Plant Operators shall hold a reactor operator license.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

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i Amendment No. If, 38, 34, 37, 117 47, 38, If, 84, 82, 85, SS, DJ,112

6.2."2.1

' Administrative controls shall be established to liait the amount of overtime worked by plant staff performing safety related functions.

These administrative controls shall be in accordance with the guidance provided by the NRC Policy Statement on working hou,s (Generic Letter 82-12).

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 position, except for (1) the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and L

(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.

6.4 TRAINING l

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Executive Director, ANO Site Operations and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Executive Director, ANO Site Operations and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except for Fire Brigade training sessions which shall be ht1d at least quarterly.

6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function 6.5.1.1 The Plant Safety Committee shall function to advise the Executive Director, ANO Site Operations on all matters related to nucleer safety.

j COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the:

l Chairman: General Manager, Plant Support Member:

Operations Manager Member:

Maintenance Manager 4

Member:

Training Manager Member:

Plant Licensing Supervisor Member:

Engineering Manager Member:

Quality Assurance Superintendent Member:

Reactor Engineering Superintendent Member:

Health Physics Superintendent j

The Executive Director, ANO Site Operations should designate in writing the Alternate Chairman in the absence of the Chairman.

l Amendment No. M. M, N, /7, 4,

117a M, 99, N9, 112

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l Amendment No. H. N, N, {1 #7, M. H.

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l Amendment No g g,j h 54,82, 99, 120

l ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall pa.ticipate as voting members in PSC activities at anv ane time.

MEETING FREQUENCY 6.5.1.4 The PSC shall meet at least once per calendar month and as convened by the PSC Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the PSC necessary for the performance of the PSC responsibil'ty and authority provisions of these technical specifications sha.. consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Safety '7mmittee shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and revisions thereto, 2) any other proposed procedures or revisions thereto as determined by the Executive Director, ANO Site Operations to affect nuclear cafety, b.

Review of all proposed tests and experiments that affect nuclear safety.

c.

Review of,all proposed changes to the Appendix "A" Technical Specifications.

d.

Review o1 all proposed changes or modifications to plant systems or equipment that affect nuclear safety, e.

Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Executive Director, ANO Site Operations and to the Chairman of the Safety Review Ccmmittee.

f.

Review of those Reportable Occurrences requiring 24-hour notification of the Commission.

Amendment No. 28, 34, 27,.A7, 54, 82, 99, 121 Jpp,112

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