ML20069B745

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Amend 172 to License DPR-51,changing TS 4.18.6 & Table 4.18-2 to Make Requirements for C-3 Repts on SG Tube Insps Consistent W/B&W STS
ML20069B745
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/19/1994
From: Beckner W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20069B749 List:
References
NUDOCS 9405310113
Download: ML20069B745 (5)


Text

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,t UNITED STATES I.g4;ffi j NUCLEAR REGULATORY COMMISSION I

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WASHINGTON. D.C. 20555 0001

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ENTERGY OPERATIONS INC.

DOCKET NO. 50-313 ARKANSAS NUCLEAR'0NE. UNIT NO. 1" l

l AMENDMENT TO FACILITY OPERATING t LCDLSE Amendment No. 172 i

License No. DPR-51 l

l 1.

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

l A.

The application for amendment by Entergy Operations,-Inc. (the licensee) dated March 19, 1993, 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.thd application, the.

provisions of the Act, and the rules and regulations' of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized j

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 Commission's regulations; D.

The issuance of this license amendment will-not be inimical to the

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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.

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1 9405310113 940519 l

PDR. ADOCK 05000313:

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Accordingly, the license is _ amended'by changas 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*

meended to read as follows:

2.

Igchnical Specifications The Technical Specifications contained in Appendix A, as revised-l through Amendment No.172, are hereby incorporated in _ the license.

The licensee shall operate the facility in accordance with the.

Technical Specifications.

3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

[h h i % L D. / b n L,u William D. Beckner, Director Project Directorate IV-1 Division-of~ Reactor Projects - III/IV Office'of Nuclear Reactor Regulation -

Attachment:

Changes to the Technical Specifications l

l Date of Issuance:

May 19, 1994 l

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1 ATTACHMENT TO LICENSE AMENDMENT N0. 172 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313

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Replace the following pages of.,the_ Appendix "A" Technical Specifications with I

the attached pages. The revised pages are identified by Amendment number and:

contain vertical lines indicating the area of change.

REMOVE PAGES INSERT PAGES li0n 110n 11001 11001-9 j

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4.18.6 Reoorts Following each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC.

This report, to be submitted 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 and tubes sleeved.

This report shall be in addition to a Special Report (per Specification 6.12.5.d) required for the results of steam generator tube inspections which l fall into Category C-3 as denoted in Table 4.18-2.

The Commission shall be notified of the results of steam generator tube. inspections which fall into Category C-3 prior to resumption of plant operation. The written Special Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

Bases 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 generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.

Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.

j Amendment No. J4,f/,54,JS6, JJ$.172 lion

TABLE 4.18-2 STEAM GENERATOR TUBE INSPECTION, 8 8

i IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Samole Size Result Action Reauired Result Action Reauired Result Action Reauired i

A minimum of C-1 None N/A N/A-N/A N/A S Tubes per S.G.2 C-2 Plug or sleeve C-1 None.

N/A N/A defective tubes and C-1 None inspect additional C-2 Plug or sleeve C-2 Plug or sleeve 2S tubes in this defective tubes and defective tubes S.G.

inspect ' additional 4',

C-3 Perform action for tubes in this S.G.

C-3 result of C-3 Perform action for first sample C-3 result of first sample.

N/A N/A C-3 Inspect all tubes Other in this S.G. plug S.G. is None N/A N/A or sleeve defect-

__C-1 ive tubes and in-Other Perform action for spect'2S tubes in S.G. is C-2 results of N/A N/A other S.G.

C-2 second samole.

Other Inspect all' tubes Special Report S.G. is in each S.G. and N/A N/A to NRC pursuant C-3 plug or sleeve to 6.12.5.d.

defective tubes.

Special' Report to NRC i

pursuant to 6.12.5.d.

NOTES:

8S=3k Where N is the-number of steam generators in the unit, and n is the number of steam j

generators inspected during an inspection.

2For tubes inspected pursuant to 4.18.3.a.3:

No action is required for C-1 results. For C-2 results in one or both steam generators plug or sleeve defective tubes. For C-3 results in one or both steam generators, plug or sleeve defective tubes and provide a Special Report to NRC pursuant to 6.12.5.d.

No more than. ten thousand (10,000) sleeves may be installed in both ANO-1 steam generators coabined.

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I Amendment No. 24, #1, $$,Jp6, JJS,172 110o1

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