ML20087N435
| ML20087N435 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/30/1984 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20087N436 | List: |
| References | |
| TAC-54446, NUDOCS 8404030454 | |
| Download: ML20087N435 (1) | |
Text
.
WWil W POWER COMPANY-231 W. MICHIGAN. P.O. BOX 2046 MILWAUKEE, WI 53201 March 30, 1984
. Mr. H.
R. Denton, Director
- Office of Nuclear-Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washingcon, D. C.
20555 i
- y Attention
- - Mr. J.
R. Miller, Chief Operating Reactors, Branch 3 s
s Gentlemen:
f DOCKET NO. 50--266 REACTOR VESSEL OUTLET NOZZLE FLAW INDICATION EVALUATION FINAL REPORTS
. POINT BEACH NUCLEAR PLANT, UNIT 1 7
Our March 23, 1984 letter concerning flaw indication evaluations advisedithat we.would forward complete reports of Southwest.Research Institute's sizing analysis and fracture analysis of the vessel outlet nozzle flaw indications by March 30.
Attached'to this letter for your review are two copies of the referenced ~ reports: " Sizing ofiUltrasonically Detected Indications in the Point-Beach Unit 1 RPV Outlet Nozzles" and
" Reactor-Vessel Outlet Nozzle-to-Shell Weld Flaw Indication
. Fracture Mechanics Evaluation for Point-Beach Nuclear Plant,
' Unit 1".
With'the transmittal of these results, we have completed our. demonstration'that'the flaw.-indications are within the limits specified-in ASME Sect' ion XI and-that the flaw indications do not' impact the continued serviceability'of.the Point Beach Unit 1 reactor.-vessel.
~
If~you have any questions about these. reports or the.
- data ' previously ' transmitted, please' contact us.
f Very truly ours,.
ce y Vice Presi ent-Nuclear Power
' C.;W.
Fay Enclosure Copy torNRC) Resident Inspector jooI
~
8404030454 840330 C
PDR ADOCK 05000266 P-PDR I
e g
m
.2
....-.2
-- ---