ML20207G659

Amend 232 to License NPF-3,revising TSs in Response to 990309 Application.Changes Increase Inservice Insp Interval & Reduce Scope of Volumetric & Surface Examinations for Reactor Coolant Pump Flywheels

ML20207G659
Person / Time
Site:	Davis Besse
Issue date:	06/08/1999
From:	Anthony Mendiola NRC (Affiliation Not Assigned)
To:
Shared Package
ML20207G664	List: ML20207G659 ML20207G666
References
NUDOCS 9906140013
Download: ML20207G659 (4)

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n UNITED STATES f

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. enmaa anni

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ElRSTENERGY NUCLEAR OPERATING COMPANY l

DOCKET NO. 50-346

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DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO._1

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 232 License No. NPF-3 1.

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

A.

The application for amendment by FirstEnergy Nuclear Operating Company (the licensee) dated March 9,1999, 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. NPF-3 is hereby amended to read as follows:

9906140013 990608 PDR ADOCK 05000346 P

PDR

(2)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 23Eare hereby incorporated in the license. FENOC shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance FOR THE U.

CLEAR REGULATORY COMMISSION

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'fy. Mendiola, Chief, Section 2

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/ th Mject Directorate ill ivision of Licensing Project Management ffice of Nuclear Reactor Regulation j

Attachment:

Changes to t e hnical Specifications Date ofissuance: June 8,1999 i

F. :.

ATTACHMENT TO LICENSE AMENDMENT NO. 232 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.

. Remove Insert k

TS 3/4 4-30 TS 3/4 4-30

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REACTOR COOLANT SYSTEM 3.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1. 2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1,2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.

APPLICABILITY: All MODES.~

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ACTION:

a. ' With the structural integrity of any ASME Code Class I component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50 *F above the minimum temperature required by NDT considerations, b.

With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200 'F.

c.

With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the component (s) to within its limit or isolate the affected component (s) from service.

d._

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5:

a.

Inservice inspection of each reactor coolant pump flywheel shall be performed at least once every 10 years. The inservice inspection shall be either an ultrasonic examination of the volume from the inner bore of the flywheel to the circle of one-half the outer radius, or a surface examination of exposed surfaces of the disassembled flywheel. The recommendations delineated in Regulatory Guide 1.14, Revision 1, August 1975, Positions 3,4 and 5 of Section C.4.b shall apply.

DAVIS-BESSE, UNIT 1 3/4 4-30 Amendment No. 232 I

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