ML19318B341
| ML19318B341 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/29/1980 |
| From: | Peoples D COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19318B339 | List: |
| References | |
| NUDOCS 8006250266 | |
| Download: ML19318B341 (2) | |
Text
/,, s Commonwealth Edison l
on7 First N: tion;l Plin, Chic go, Illinois (O'
(
7 Address Reply to: Post Office Box 767
\\
Chicago, Illinois 60690 May 29, 1980 Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
LaSalle County Units 1 and 2 Response to IE Inspection Report Nos. 50-373/80-12 and 50-374/80-08, NRC Docket Nos. 50-373 and 50-374 Reference (a):
G. Fiorelli letter to B. Lee, Jr. dated April 26, 1980
Dear Mr. Keppler:
The following is in response to the inspection conducted by Mr.
I.
T. Yin on March 12-14, 1980 at the LaSalle County site, on March 18-19, 1980 at the corporate of fice of Sargent and Lundy Engineers, and on March 19, 1980 at Commonwealth Edison Company, of activities at the LaSalle rounty Station, Units 1 and 2.
Reference (a) indicated that certain activities appeared to be in non-compliance with NRC requirements.
These activities are addressed in the enclosure to this letter.
Please refer any additional questions you may have on this matter to this office.
Very truly yours, l
L D.
L. ?eo es Director of Nuclear Licensing Enclosure 4171A MAY 3 01980
- 0062502b$
NRC Docket Nos. 50-373 50-374 ENCLOSURE Infraction 10 CFR 50, Appendix B, Criterion III states, in part, that " Measures shall be established to assure that applicable regulatory requirements and the design basis... are correctly translated into specifications, drawings, procedures, and instructions."
Section 3 of the Commonwealth Edison Company Topical Report, CE-1-A, "QA Program for Nuclear Generating Station Revision 9, dated July 16, 1979, endorsed by the FSAR Chapter 17, states, in part, "The fundamental vehicle for design control involves multi-level review and/or evaluation of design documents by ind.ividuals or groups other than the original designer or designer's immediate supervisor whose authority and responsibility are identified and controlled by written procedures.
The design documents include, but are not limited to, system flow diagrams, design and construction specifications, load capacity data sheets, design reports, equipment specifications, process drawings.
Design calculations are also subject to two or more levels of evaluation or review including that performed by the originator plus review and audit by Station Nuclear Engineering where design work is performed by the Architect Engineer or other vandors or contractors."
Contrary to the above, the control for small bore piping suspension system design was considered deficient in that procedural requirements, personnel qualification requirements, interface requirements, and final review and approval had not been established for the design and engineering groups performing the work.
Corrective Action Taken and Results Achieved:
Sargent and Lundy is in the final process of revising their Project Instruction PI-LS-16,-Appendix K, Small Piping Guidelines, to provide clearer responsibilities and work procedures.
Project Instruction PI-LS-19, For Record Review, has also been revised to clarify the inspector's concern.
The project instruction now states that the support drawings will be compared with the stress output including computer printout isometric drawing.
Corrective Action To Be Taken To Avoid Futher Noncompliance:
The only document utilized by Sargent & Lundy in the calculation and review of small piping supports is PI-LS-16, Appendix K.
Other documents in use prior to this time are all, in essence, similar and are being incorporated into PI-LS-16.
Date When Full Compliance Wil Be Achieved:
PI-LS-19 has been revised.
PI-LS-16, Appendix K, will be issued by June 10, 1980.
_