ML20010A684
| ML20010A684 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/28/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20010A685 | List: |
| References | |
| DPR-51-A-059 NUDOCS 8108120032 | |
| Download: ML20010A684 (4) | |
Text
4 UNITED STATES
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3 NUCLEAR REGULATORY COMMISSION E..hdI WASHINGTON, D. C. 20555
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~ ARKANSAS POWER & LIGHT COMPANY DO,CKQ!i0. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO.1 AMENDME'tT TO FACILITY CPERATING LICENSE Armndment No ' 59 License No. DPR-51 1.
The Nuclear Regulatory Comissien (the Comission) has found that:
A.
The application. for amendment by Arkansas Pcwer and Light Company (the licensee)' dated June 10, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comissi,on; There is reasonable assurance (i) that the activities authorized C.
by this amendment can be conductec without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; The issuance of this amendment will not be inimical to the comon D.
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 C?R Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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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. DPR-51 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications. contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall-operate the facility in accordance with the' Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Jo$n F. Stolz, Chief GjpratingReactorsBranch#4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: -July 28, 1931 l
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P ATTACHMEtiT TO LICE!!SE Af tEfiDf1EilT fiO. 59 FACILITY OPERATIi1G LICEliSE l10. DPR-51 DOCKET fi0. 50-313 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendnent number and contains a vertical line indicating the area of change.
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r 6.0 ADMINISTRATIVE CohTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE' 6.2.1 The offsite organiration for facility =anage=ent and tech-nical support shall be as shown on Figure 6.2.-l.
FACILITY STAFT 6.2.2 The Facility organination shall be as shown on Figure 6.2.-2.
Each on duty shift shall be co= posed of at least the =ini=u=
shift crew co= position shown in Table 6.2.-l.
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 comparaole position, except for (1) the Health Physics Supervisor who sh tll meet or exceed the qualifications of Regulat;ry 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 analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training progra= for the facility staff shall be =aintained and shall meet or exceed the require-
=ents and reco==endations of Section 5.5 of ANSI N:t 1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for fire protection training shall be
=aintained and shall =eet or exceed the requirements of Section 27 cl the NFPA Code-1975 with the exception of frequency of training which shall be held at least quarterly.
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6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Co==ittee (PSC) Function 6.5.1.1 The Plant Saf ety Cc==ittee shall function to advise the General Manager on all =atters related to nuclear safety.
l COMFOSITION 6.5.1.2 The Plant safety Cc==ittee shall be co=posca of the:
(See Page 121) l Amendment fio. X, E, y* Z
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