ML19319D556
| ML19319D556 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, Davis Besse  |
| Issue date: | 08/23/1976 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Rodgers J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8003170678 | |
| Download: ML19319D556 (2) | |
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J. Stolz Docket No. 50-302 L. Engle E. Hylton J. Thomas S. Hou Florida Power Corporation ATTN: Mr. J. T. Rodgers ACRS (16)
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Assistant Vice President and Nuclear Project Manager IE (3)
P. O. Box 14042 H. Smith St. Petersburg, Florida 33733 bec:
J. R. Buchanan, NSIC Gentlemen:
T. B. Abernathy, TIC STATUS OF Tile BABC0CK & WILCOX REDESIGN OF TIIE SURVEILLAflCE SPECI'iEN HOLDER TUBES FOR B&W 177 FA PLANTS T.!s letter is to infom you on the present status of the new design of the Babcock and Wilcox (B&W) surveillance specimen holder tube (SSHT) for the B&W 177 FA plants and how these matters interface with our review for Crystal River, Unit 3 (CR-3).
Final flRC approval of the new B&W 177 FA SSHT will not occur until all B&W Topical Reports on this subject have been submitted for IRC review and approval.
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We are concerned that installation of an NRC approved B&W 177 FA SSHT on CR-3 cannot occur in time to avoid a major impact on the CR-3 OL scheduling.
The installation of the new B&W SSHT for CR-3 of the same design as approved by the NRC for prototype testing in the Davis Besse Nuclear Power Station, Unit 1 (DB-1) may be in order for CR-3.
We believe these matters require your attention at this time.
In the event that design modifications for the new B&W SSlfT are indicated from the tests results on DB-1, the bolt-on-design could allow modifications to be made at CR-3 which might preclude difficult drilling and tapping operations when CR-3 was in an irradiated condition.
For your infonnation the vibratory testing of the new B&W SSHT which was to commence with the hot functional testing for DB-1 has now slipped from August 27, 1976 to September 28, 1976.
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. o M 2 3 576 Florida Power Corporation We are presently reviewing tne B&W Topicals:
BAW 10033, "Prototyne Vibration Measurement Program for Reactor Internals," August 5,1976; and BAW lug 51 Supplement 1, " Design of Reactor Internals and Incore Instrument !!ozzles f or Flow Induced Vibration-Structural Analysis of 177 FA Redesign fpecimen Holder Tube," fugust 6,1976.
The B&W Topical, BAW 10039, Supplement 1, " Prototype Vibrat Ica Results for B&W 177 FA Two Loop Plant," is presently estimated to be sutsaitted for flRC review and approval about the end of October 1976.
We request that you keep us infonned of your decision regarding these matters and please call us if you have any questions about these matters.
Sincerely, Original signed By' fennis P, Allisog
.Nohn F. Stolz, Chief Light Water' Reactors Branch l10. 1 Division of Project Managernent cc: iir. S. A. Brandimore Vice President and General Counsel P. O. Box 14042 St. Petersburg, Florida 33733 itr. Kenneth E. Suhrle Manager, Licensing Babcock & Wilcox Company P. O. Box 1260 Lynchburg, Virginia.M505 LWR 1 F
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