ML19262C545
| ML19262C545 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/04/1980 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | Peoples D COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8002140399 | |
| Download: ML19262C545 (3) | |
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o UNITED STATES Eyy'.,-gf/j NUCLEAR REGULATORY COMMISSION JJ/ j WASWNGTON D. C.20555 s,, v/
FEB 4 1980 Docket Nos.: STN 50-454/455 STN 50-456/457 Mr. D. Louis Peoples Director of Nuclear Licensing Comonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 Ocar Mr. Peoples:
SUBJECT:
NRC STAFF CONFIRMATORY PIPING ANALYSIS FOR BYRON /BRAIDWOOD The NRC staff has recently instituted a program of perfonning an independent confirmatory piping analysis for each plant undergoing an operating license stage of review.
For the Byron and Braidwood Stations this analysis will be performed by our contract personnel at tha Argonne National Laboratory (ANL).
The purpose of this independent analysis will be to verify that the subject piping system meets the applicable ANSI /ASME Code stress criteria. We do not intend to resolve differences between our calculated stresses and those that you have calculated unless unusually large discrepancies are found, or unless Code criteria are not met.
This program will allow the NRC staff to verify on a sampling basis that you have correctly modeled piping, correctly used computer codes, and adequately accounted for the piping's as-built condition.
In,rder to proceed with our analysis, we require certain information. Upon re ;eipt of this information, ANL will evaluate it to determine if additional i, fannation or clarification is required.
Following the initial review we b 'ie to schedule a site visit to acquaint the ANL personnel with the plant a r.o ? e specifically the piping system under review. At that time we can discuss the piping analysis with your design engineers and obtain any addi-tional information required.
Therefore, for the 1FWO3DC-16" Loop 3 Feedwater line (figure 3.6-27 of the FSAR), we request that you transmit two copies of the following information to ANL and four copies to us for the inclusion in the docket files and the NRC staff's use.
FEB 4 1980 Mr. D. Louis Peoples
- piping layout and isometric drawings sufficient to model the system support drawings with support and hanger spring rates the piping design specification (4) valve weights and centers of gravity (5) appropriate response spectra (6) appropriate anchor point movements (7) any design change notices not yet incorporated into the piping or support drawings (later notices should be forwarded as issued).
As our analysis proceeds, we will also require the submission of certain analytical results for comparative purposes, such as the ASME Code required Design Reports.
Sincerely,
. /1
. 3 db f \\ltfd t-Q k t.uc L. S.'Rdbenstein, Acting Chief Light Water Reactors, Branch No. 4 Division of Project Management cc: See next page
Coninonwealth Edison Company ccs:
Mr. William Kortier Atomic Power Distribution Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 Paul M. Murphy, Esq.
Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois 60603 Mrs. Phillip B. Johnson 1997 Stratford Lane Rockford, Illinois 61107 fis. Julianne Mahler Center for Governmental Studies florthern Illinois tiniversity DeKalb, Illinois 60115 C. Allen Bock, Esq.
P. O. Box 342 Urbana, Illinois 61801 Thomas J. Gordon, Esq.
Waaler, Evans & Gordon 2503 S. Neil Champaign, Illinois 61820 Ms. Bridget Little Rorem Appleseed Coordinator 117 florth Linden Street Essex, Illinois 60935