ML20057G263

Provides Clarifications & Corrections to 931005 TS Amend Requesting Renewal of voltage-based SG Tube Interim Plugging Criteria for Unit 1 Cycle 8,in Response to NRC Review of Subj Submittal

ML20057G263
Person / Time
Site:	Catawba
Issue date:	10/14/1993
From:	Rehn D DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9310210131
Download: ML20057G263 (4)

Text

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Du$:e M2r Company DLRim Catwk Nudear Gerwrahon Depanmen:

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@03)D13203 O!hce York SC29745 603LU13125 Fox DUKEPOWER October 14,1993 U. S. Nuclear Regulatory Conunission Attention: Document Control Desk Washington, D. C.

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Subject:

Catawba Nuclear Station, Unit i Docket No. 50-413 Supplement to Technical Specification Amendment Renewal Of Steam Generator Tube Interim Plugging Criteria for Unit I Cycle 8 On October 5,1993, Catawba Nuclear Station submitted a proposed Technical Specification Amendment requesting renewal of the voltage-based steam generator tube interim plugging criteria for Unit I for Cycle 8. Review of this submittal by the NRC staffindicated several statements needing clarification and errors needing correction within the No Significant Hazards Consideration. The following clarifications and corrections to the October 5,1993 submittal are being provided:

1) 7 On page 1 of 5 of the No Significant Hazards Consideration, the second sentence in the first paragraph under standard I should state " Based on the existing data base, the limiting RG 1.121 criterion for tube burst capability of 3 times nonnal operating pressure differential is satisfied with 3/4" diameter iubing with bobbin coil indications with signal amplitudes less than 4.2 volt,, regardless of the indicated depth measurement. "

2)

On page 3 of 5 of the No Significant Hazards Consideration, the second sentence in the first paragraph under standard 3 should state "RG 1.121 describes a method acceptable to the NRC staff for meeting GDCs 14,15, 31, and 32 by reducing the probability or the consequences of steam generator tube mpture."

3) The conchision on page 4 of 5 of the No Significant Hazards Consideration should state " Based on the preceding analysis, it is concluded that using voltage-based interim steam gmerator tube plugging criteria for removing tubes from service is acceptable and the proposed license amendment involves a no significant hazards consideration as defm' ed in 10 CFR 50.92."

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Page 2 Pursuant to Id CFR 50.91 '(b)(1), the appmpriate South Carolina official is being provided

-;a copy of these changes to the amendment request.

Very truly yours, t

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- D. L. Rehn RKS/

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Nuclear Regulatory Commission -

L October 14, 1993-j.y Page 3 xc; Mr; S; D.- Ebneter I

Regional-Administrator, Region-II U. S; Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, GA. 30323 E

Mr. Heyward Shealy, Chief ppip::

Bureau'of Radiological Health

' South Carolina'Depanment'of Health &

Environmental Control p

2600 Bull Street-

- Columbia, SC 29201

Mr. R. J.- Freudenberger

NRC Resident Inspector

. Catawba Nuclear Station-

- Mr. Roben Ec Martin, Project Manager

.ONRR-

'Mr. William T. Russell, Associate Director Inspection & Technical. Assessment ONRR

. American Nuclear Insurers c/o Dottie Shennan, ANI Library The Exchange, Suite 245

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270 Farmington Avenue Farmington, CT 06032

' M & M Nuclear Consultants

.I166 Avenue of the Americas New York, NY 10036-2774 INPO Records Center

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-D. L. Rehn, being duly sworn, states that he is Site Vice-President, Catawba Nuclear Station; that he is authorized on the part of said company to sign and file with the Nuclear Regulatoryi. Commission this revision to the Catawba Nuclear Station Technical Specifications, Appendix A to License No. NPF-35; and that all statements and matters set forth therein are true and correct to the best of his knowledge.

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DI L. ReTn Subscribed and sworn to before me this /## day of Oct

,1993.

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