ML19343D341
| ML19343D341 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/28/1981 |
| From: | Trimble D ARKANSAS POWER & LIGHT CO. |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19343D342 | List: |
| References | |
| 2R-0481-09, 2R-481-9, NUDOCS 8105040318 | |
| Download: ML19343D341 (2) | |
Text
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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKAfGAS 72203 [501)371-40C0 April 28, 1981 2R-0481-09 Mr. Thomas H. Novak Assistant Director for Operating Reactors Division of Licensing U. S. Nuclear Regulatory Comm.
Washington, D.C.
20555
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Fracture Toughness - Response to Item 1 Subtopic 4 of NRC's August 5, 1980 Letter
_(File: 2-1510)
Gentlemen:
The attached report (Attachment 1), which was generated by Combustion Engineering, describes the fracture evaluation of the reactor coolant pump motor seismic snubber lugs for Arkansas Nuclear One - Unit 2.
This evaluation was performed to respond to Item I subtopic 4 of your letter of August 5, 1980. The fracture evaluation, comparing the stress intensity factor computed assuming large flaws to the icwer bound toughness suggested by NUREG-0577, demonstrates an adequate safety margin against brittle fracture. Also, attached are the CE report " Fracture Mechanics Procedures for Primary Component Support Toughness Evaluations", (Attachment 2), and the RCP motor lug infonnation supplied by General Electric (Attachment 3).
These documents were either referenced in or used to develop the snubber lug evaluation report.
This analysis was perfomed in accordance with the proposed method as submitted to the NRC in our letter of January 15, 1981.
We would be pleased to answer any questions you may have on the. report.
Very truly yours, Y
f oavid c. Trimble, 8105 0 4 031T-Manager, Licensing DCT:DFS:1p Attachments MEMBEA MIDDLE SOUTH UTILmES SYSTEM
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