ML20072M286
| ML20072M286 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/25/1983 |
| From: | Clark R, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20072M288 | List: |
| References | |
| DPR-51-A-073, NPF-06-A-041 NUDOCS 8304010211 | |
| Download: ML20072M286 (8) | |
Text
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UNITED STATES e
NUCLEAR REGULATORY COMMISSION j
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ARKANSAS POWER & LIGHT COMPANY DOCKET fl0. 50-313 ARKANSAS NUCLEAR ONE, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 73 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Conany (the licensee) dated February 25, 1983, coglies 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 CPR Part 51 of the Comissiort's regulations and all applicable mquirements have been satisfied.
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8304010211 830325 PDR ADOCK 05000313 P
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. DPR-51 is hereby amended to read as follows Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 73, 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 Joh f F. Stolz, Chief j Operating Reactors BM h #4 M' ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 25, 1983
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 73
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FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following page of the Appendix A Tecliniiai Specifications with the enclosed page. The revised page is identified by Amendment Number and contains a vertical line indicating the area of change.
Page 1 41 o
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The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures
" totalling less than 20% of the~ individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body, dose received from external sources shall be assigned to specific major work functions.
6.12.2.3 Monthly Operating Report Routine reports of operating statistics which include:
1.
Average Daily Unit Power Level 2.
Operating Data Report 3.
Unit Shutdowns and Power Reductions 4.
Narrative Summary of Operating Experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the appropriate Regional Office by the fifteenth of each month following the calendar month covered by the report.
6.12.2.4 Annual Report All challenges to the pressurizer electromatic relief valve (ERV) and pressurizer safety valves shall be reported annually.
6.12.3 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent recurrence, shall be reported to the NRC as required below.
Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
6.12.3.1 Prompt Notification With Written Followup The types of events listed below shall be reported as expeditiously as possible, but within 24-hours, by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the appropriate Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks. A copy of the confirmation and the written followup report shall also be sent to the Director, Office of Management and Program Analysis, USNRC. The
. ritten report shall include, as a minimum, a completed copy of a licensee w
event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
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Amendment No.#,24,2F#,73
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NUCLEAR REGULATORY COMMISSION 3
WASHINGTCN, D. C. 20555 ARKANSAS POWER & LIGHT COMPANY
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DOCKET fl0. 50-3G8 ARKANSAS NUCLEAR ONE, Ur1IT F10. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 41 License No. flPF-G 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Co@any (the licensee) dated February 25, 1983, coglies with the standards and requirements of the Atomic Energy Act of 1954, as annnded (the Act), and,the Comission'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 Comission; C.
There is reasonable assurance (1) 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 CPR Part 51 of the Comission's regulations and all applicable mquirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 2.C.(2) of Facility Operating License No. NpF-6 is hereby amended to read as follows:
Technical Specifications The Technical Specifications conta.ined in Appendix A, as revised through Amendnent No. 41, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY C0?tilSSION Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: liarch 25, 1933 k
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ATTACHMENT TO LICENSE AMENDMENT NO. A1
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FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by Amendment Number and contains vertical lines indicating the area of change.
Page 6-15 s
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ADMINISTRATIVE CONTROLS ANNUAL rep 0RTS1/
knnual reports covering the activities of the unit as d6 scribed 6.9.1.4 below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis for the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their assopated man rem exposure according to work and job functions, e.g.,
reactor operations and surveillance, inservice inspection.
routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
b.
The complete results of steam generator tube inservice inspec-tions performed during the report period (reference Specifica-tion 4.4.5.5.b).
c.
Documentation of all challenges to the pressurizer safety valves.
l 1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
2/
This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.
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4RKANSAS - UNIT 2 6-15 Amendment No. E,41 l
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