ML19320A282
| ML19320A282 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/20/1977 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19320A275 | List: |
| References | |
| NUDOCS 8004210566 | |
| Download: ML19320A282 (7) | |
Text
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UNITED STATES 8
'.n NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 a
ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO. 1 At1ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29 License No. DPR-S1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amenoment by Arkansas Power & Light Company (the licensee) dated November 1,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulations set forth in 10 CFP Chapter I; 8.
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 rN sonable assurance (i) tnat the activities authorizeo by this anendment ;an 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 Conmission's regulations and all applicable requirer. eats 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 amendment and paragraph 2.c(2) of Facility License flo. OPR-51 is bereby amended to read as follows:
(2) Technical Specifications The Technical Specifications. contained in Appendices A and B, as revised through Amendment No. 29, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on January 1,1975.
FOR THE.4UCLEAR REGULATORY COMitISS10fl I
t, ' *.
l-Don K. Davis, Acting Chief.
Operating Reactors Branch #2 Division of Operatino Reactors
Attachment:
Changes to the Technical Specifications Date of Issbance:
Decenber 20, 1977 l
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ATTACMENT TO LICENSE AMENDMENT NO. 29 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Accomplish page changes to the Appendix A portion of the Technical Specifications as noted below. The changed areas on the revised pages are identified by a marginal line, 4
Remove Existing Page Add Revised page 110n 110m 140 140 141 1 41 142 149 142a (deleted) e l
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry completely to the point of exit.
b.
The steam generator shall be determined operable after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.18.2.
4.18.6 Reports Following each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC. This report, to be sutstitted within 45 days of inspection completion, shall include:
a.
Number and extent of tubes inspected; b.
Location and percent of wall-thickness penetration for each indication of an imperfection; and c.
Identification of tubes plugged.
This report shall be in addition to the report of results of steam generator tube inspections which fall into Category C-3 and which require prompt notification of the NRC per Specification 6.12.3.
I Bases i
The surveillance requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam gen-erator tubes is based on a modification of Regulatory Guide 1.83, Revi-sion 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes ia the event that there is evidence of mechanical damage or progressive degrad-
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ation due to design, manufacturing errors, or inservice conditions that lead to corrosion. Inservice inspection of steam generator iubing also provides a means of characterizing the nature and cause of any tube
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degradation so that correr.cive measures can be taken.
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Amendment No. 2/, 29 110m
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6 12 REPORTING 6.12.1 REQUIREMEN1S In addition to the Code of Federal p
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%. lose assignment to various duty functions may be estimates based
, m jocket dosih.ater, 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*4 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 Manage-ment Infonnation and Program Control, 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.
6.12.3 'Reportabic Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, 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 orig-inal 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Directo of the appropriate Regional Office, or his designate no later than th first working day following the event, with a written followup report E thin tso weeks. A copy of the confimation and the written followup repoi'..,nall also be sent to the Director, Office of Management Information and Program Control, USNRC. The written report shall include, as a minimum, a completed copy of a licensee event report fom.
Infomation provided en the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
Amendment No. 9, U, 29 141 e
-m s-(a) Fail ire of' the. reactor protection. systen or ot t.cr sptems subj cet to limiting safety 'systein settings to initiate the rnctired protect ive-
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< function.by the. time a monitored parameter ir.ich tl.c setpoint speei-fled as ;the !!.miting safety system set ting in t he rechnical Speci fi-cations.or failure to complete the required prot cetive function.
NOTE:
Instrument drif t ' discovered as a result of-te st ing need not be report ed under th's. iten.but cry be ceportable under iter; (e), (f), or 6.12. 3. 2(a).
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142 Amendment No.~JA,f 29 D-m.
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