ML19308B031

Forwards Proposed Tech Specs Re Inservice Insp of once- Through Steam Generators

ML19308B031
Person / Time
Site:	Oconee
Issue date:	11/30/1976
From:	Parker W DUKE POWER CO.
To:	Rusche B, Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML19308B032	List: ML19308B031 ML19308B036
References
NUDOCS 7912120788
Download: ML19308B031 (4)

Text

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NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Duke ?o cr Co nany 11/30/75 lr. I,enari C. 'usc ic i CharlO*.02, Co r th Ca r ? '. i nt. DATE RECEIVED "r.

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November 30, 1976

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• ~~ N q{ (lPl M,'f ccewn , lCGu { ^ ~ l'. T Mr. Benard C. Rusche DEC 1976 > k' '

Director of Nuclear Reactor Re cion % $ 7-

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U. S. Nuclear Regulatory Commia 0~*ae c' '0...-

Washington, D. C. 20555 b g j e6 m Attention: Mr. A. Schwencer l j

Re: Oconee Nuclear Station l Docket Nos. 50-269, -270, -287

Dear Mr. Rusche:

Your letter of September 21, 1976 requested that we submit a request for a license amendment for the Oconee Nuclear Station to incorporate requirements concerning the operability and inservice inspections of l steam generators. Model Technical Specifications were provided which I were to be appropriately adapted to the specific format and number of steam generators in the Oconee units. In response to this request and pursuant to the provisions of 10CFR50, 550.90, the attached amendment I to Appendix A to Facility Operating Licenses DPR-38, -47, and -55 is requested. {

The attached specification for the inservice inspection of the Oconee once-through steam generators (OTSG) is consistent with the intent of the model specifications in endeavoring to assure the integrity of the steam generators. As described, the two OTSG's per Oconee unit will normally be inspected on an alternating schedule. The initial sample of each inspection will consist of 6 percent of the total tubes per unit.

Tube plugging and subsequent samples, if necessary, will be taken dependent upon the results of the preceding sample. In this manner, adequate assurance of the satisfactory condition of the OTSG's will be obtained. This specification differs from the model specification in that complete steam generator tube inspection is not considered necessary upon a C-3 inspection result. The steam generator tube sample size, corrective actions and subsequent ins'e r ion frequencies proposed in this specification are consistent with the requirements of Section XI of the ASME Code, and where feasible, incorporats the principles of Regulatory Guide 1.83, 7tev.1, " Inservice Inspection of Pressurized Water Reactor Steam Genert.cor Tubes."

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!!r. Ilen.ird C. Rusche Page 2 November 20, 1976 Although primary-to-secondary leakage through steam generators may be indicative of a loss of tube strength or pressure boundary integrity, there is no known correlation between leakage rate and tube strength.

The if.nitation of 1 gpm leakage through the steam generator tubes is considered to be overly restrictive in the model technical specification.

Adequate assurance of safe operation will be providad by adhering to the present Oconce. Technical Specifications 3.1-6, " Leakage," and 3.13,

" Secondary System Activity." .

Experience at Oconee with four inservice inspections of the steam generators (two for Oconee 1 and one cach f or Oconee 2 and 3) have revealed essentially no measurable wall thinning. Two small steam ,

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generator leaks have been experienced (see Reportable Occurrence l Reports R0-269/76-17 and R0-287/76-10) which are considered to have been l the result of isolated manufacturing defects. For this reason, the l requirement to perform steam generator inspections for isolated manu-  !

facturing defects, not related to wall thinning, have not been included. )

The attached specification is considered to provide adequate assurance of conti"; a steam generator integrity while p'ermitting ma::imum operating

! flexibility for the Oconee units.

I Ver truly yours, I rn

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William O. Parker, Jr.( q MST:vr Attachment '

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Mri th na rit (:. Rosche l'a ne !

November 30, 1976 WILLIN! 0. PARKER, JR., being duly sworn, states that he is Vice President of l Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear. Regulatory Commission this request for amendment of the Oconce Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38. -47 and DPR-55; and that all statements and matters set forth therein are true and correct to the best of his knowledge.

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William O. Parker, Jr. , VW President ATTEST:

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Lewis F. Camp, Jr.

Assistant Secretary (Seal)

Subscribed and sworn to before me this 30th day of November, 1976.

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' Notary Public (Notarial Seal) j My Commission Expires:

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