ML19322B461
| ML19322B461 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/27/1975 |
| From: | Thies A DUKE POWER CO. |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.083 NUDOCS 7912030300 | |
| Download: ML19322B461 (2) | |
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DuxE POWER COMPMI Powra Sc Loneo 422 Sot *Tu Curacn STazrT. CnAntoTTE.N. C asaos A. C. Tu rcs s,amo. v c c p.c..os.,
P. o. Box 217e
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w February 27, 1975 g
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wag w Mr. Angelo Giambusso, Director Division of Reactor Licensing
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U. S. Nuclear Regulatory Commission
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Washington, D. C.
20555
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Re:
Oconee Nuclear Station Docket Nos. 50-269, -270, -287
Dear Mr. Giambu" o:
On August 30, 1974, a proposed revision to the Oconee Nuclear Station Technical Specifications was submitted to incorporate a program for steam generator tubing surveillance consistent with Regulatory Guide 1.83.
This proposed technical specification revision was in response to Mr. Karl R. Goller's letter of July 18, 1974.
Subsequent to this submittal, additional information concernJ.ng once-through steam generator (OTSG) tubing surveillance has become available to us and should be incorporated into the proposed technical specification.
Therefore, it is requested that my submittal of August 30, 1974 be withdrawn from further consideration and review.
The Babcock & Wilcox Company forwarded comments on Regulatory Guide 1.83 to the Secretary of the Commission on August 26, 1974.
It was B&W's position that Regulatory Guide 1.83 did not adequately reflect the important design and operating features of the OTSG which con-tribute to steam generator tube integrity. The essential differences between the OTSG and recirculation type steam generators as described in this submittal are:
1.
The OTSG is not as susceptible to steam side corrosion attack because of the use of full flow condensate polishing with volatile chemical additives.
2.
Solids, such as sodium phosphate, are not added.
3.
The straight tube, straight shell configuration and broached tube support plate design minimize possible locations of stagnation.
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Mr. Angelo Giambusso Page 2 February 27, 1975 4.
The once-through mode of operation eliminates bulk concentrations of impurities.
5.
Testing has been performed to assure freedom from vibration damage.
During refueling of Oconee Unit 1, the steam generators were inspected using the program described in Regulatory Guide 1.83.
Information from this inspection is being evaluated; however, preliminary results indicate that the Unit 1 steam generators are exceptionally clean and free of detectable defects.
Duke Power Company is presently re-evaluating its program for steam generator tubing surveillance to properly reflect the design and operating features of the once-through steam gcs.rator and to incorporate experience gained during the Oconee Unit 1 steam generator inspection.
Upon completion of this program re-evaluation, appropriate technical specifications for steam generator tubing surveillance will be submitted.
Therefore, the request for amendment of the Oconee Nuclear Station Technical Specifications dated August 30, 1974 is rescinded.
Very truly yours, L'?
3 A. C. Thies ACT:vr r
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