ML20073B373
| ML20073B373 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/04/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20073B377 | List: |
| References | |
| DPR-51-A-074 NUDOCS 8304120302 | |
| Download: ML20073B373 (4) | |
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'8, UN TED STATES E
NUCLEAR REGULATOGY COMMISSION o
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- j WASHINGTON, D. C. 20506 i
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j ARKANSAS POWER & LIGHT COMPANY DdCKETNO.50313 4
ARKANSAS NUCLEAR ONE. UNIT NO.1 1
AMEN 9 MENT TO FACILITY OPERATING LICENSE Amendnent No. 74 License No. DPR-51
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated February 20, 1979, as supplemented August 18, 1982, November 30, 1982, December 23, 1982, and February 15, 1983, 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; 8.
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 (11) 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 commen defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable mquirements '
have been satisfied.
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R304120302 830404 PDR ADDCK 05000313 P
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Accordingly, the license is amended by changes to the Technical 4
Specifications as indicated in the attachment to this license j
amendment, and paragraph 2.c.(2) of Facility Operating License No. 9PR-51 is hereby amended to read as follows:
Technical Specifications i
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The Technical Specifications contained in Appendices A and B. as revised through Amendment No. 74, art i
hereby incorporated in the license. The licensee shall operate the facility in accordance with the'
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Technical Specifications.
I 3.
This license amendment is effective as of the date of its i
issuance.
4 FOR THE NUCLEAR REGULATORY C0fEISSION l.
j h FaStolz Chief Op rating Reactors B ch #4 4
vision of Licensing '" ~
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Attachmtnt:
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Char.ges to the Technical Specifications Date of Issuance: April 4,1983 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following page of the Appendix "A" Technical Specifications with the encibsed p_ age. The revised pag ~ e is identified by Amendment
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number and contains. a.' vertical line indicating the area of change.
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IS-261 Item Component Exception 6.4 Bolting 20 Not Applicable 6.6 Integrally Welded Not Applicable Valve Supports 4.2.3 The structural integrity of the reactor coolant system boundary shall be maintained at the level required by the original acceptance standards throughout the life of the station. Any evidence, as a result of the tests outlined in Table 15-261 of Section XI of the code, that defects have developed or grown, shall be investigated.
4.2.4 To assure the structural integrity of the reactor internals throughout the lif.e of the unit, the two sets of main internals bolts (connecting.the core barrel to the core support, shield and to the lower grid cylinder) shall remain in place and under tension..This will be verified by visual inspection to determine that the welded bolt locking caps remain in place. All locking caps will be inspected after hot functional testing and whenever the internals are removed from the vessel during a refueling or i
maintenance shutdown. The core barrel to core support shield caps l
will be inspected each refueling shutdown.
l 4.2.5 Sufficient records of each inspection shall be kept to allow comparison and evaluation of future inspections.
4.2.6 Surface and volumetric examination of the reactor coolant pump flywheels will be conducted coincident with refueling or maintenance shutdowns such that during 10 year intervals all four reactor coolant pump flywheels will be examined.
Such examinations will be performed to the extent possible through the access ports, i.e., those areas of the flywheel accessible without motor disassembly. The surface and volumetric examination may be accomplished by Acoustic Emission Examination as an initial examination method. Should the results of the Acoustic Emission Examination indicate that additional examination is necessary to ensure the structural integrity of the flywheel, then other appropriate NDE methods will be performed on the area of concern.
1 4.2.7 The reactor vessel material irradiation surveillance specimens removed from the reactor vessel in 1976 shall'be installed, irradiated in and withdrawn from the Dav'is-Besse Unit No. 1 reactor vessel in accordance with the schedule shown in Table 4.2-1.
Following withdrawal of each capsule listed in' Table 4.2-1, Arkansas Power & Light Company shall be responsible for testing the specimens and' submitting a report of test results in accordance with 10CFR50, Appendix H.
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Amendment No. 72, 29, 22,,,.74 i
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