ML20206H431

Amend 98 to License DPR-51,deleting Tech Specs Re Reactor Vessel Matl Surveillance Program

ML20206H431
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/20/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206H415	List: ML20206H412 ML20206H431 ML20206H434
References
NUDOCS 8606260071
Download: ML20206H431 (4)

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• UNITED STATES

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I,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 23555 l

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ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-51

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Arkansas Power and Light Company (the licensee) dated September 3, 1985, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) 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 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 Commission's regulations and all applicable requirements have been satisfied.

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:

8606h60071 860520 PDR ADOCK 05000313 P PDR

Technical Specifications

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98, 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.

s FOR THE NUCLEAR REGULATORY COMMISSION i .

L Joh'n . Stolz, Directo 4

PWR Project Directorate #6 Bisision of PWR Licensing-B

Attachment:

Changes to the-Technical

Specifications Date of Issuance

May 20,1986 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following pages of 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.

i Remove Insert 77 77 77a --

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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 the 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 life 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 {

maintenance shutdown. The core barrel to core support shield caps will be inspected each refueling shutdown.

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.

Bases The surveillance program has been developed to comply.with the applicable edition of Section XI and addenda of the ASME Boiler and Pressure Vessel Code, Inservice Inspection of Nuclear Reactor Coolant Systems, as required by 10CFR50.55a, to the extent practicable within limitations of design, geometry and materials of construction.

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Amendment No. 22,29,22,74,77,98 77 4- - . -