ML19338G408
| ML19338G408 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/21/1980 |
| From: | Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8010290228 | |
| Download: ML19338G408 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION 3,
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OCT 21 1980 Docket No. 50-373 Docket No. 50-374 Commonwealth Edison Company ATTN:
Mr. Cordell Reed Vice President Post Office Box 767 Chicago, IL 60690 Gentlemen:
Thank you for your final report dated October 8, 1980, pursuant to 10 CFR 50.55(e) regarding small pipe hanger deficiency. We will complete our review of this matter during a future inspection.
Your cooperation with us is appreciated.
Sincerely,
/n.[G.Fiorelli, Chief 7/d'uus M 4
Reactor Construction and Engineering Support Branch cc w/ltr dtd 10/8/80:
Mr. J. S. Abel, Director of Nuclear Licensing Mr. L. J. Burke, Site Construction Superintendent Mr. T. E. Quaka, Quality Assurance Supervisor Mr. R. H. Holyoak, Station Superintendent Mr. B. B. Stephenson Project Manager Central Files Reproduction Unit NRC 20b AE0D Resident Inspector, RIII PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General 8 010290 QN
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October 8, 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 Station Unit 1 Small Pipe Hanger Design Deficiency 10 CFR 50.55(e) Final Report NRC Docket No. 50-373 Reference (a):
J. S. Acel letter to J.
G.
Keppler dated September 26, 1980
Dear Mr. Keppler:
Commonwealth Edison notified Mr. Cordell Williams of your office on September 10, 1980, of safety related 2" & under pipe hanger deficiencies at LaSalle County Station Unit #1.
Specifically, a recent NRC inspection at the site identified the following items associated with 2" and under pipe hanger design work:
(1) Design work was ceing performed using guioelines in lieu of approved procedures.
(2) Design review standards were not being maintained as controlled documents.
(3) Site oriented training of personnel involved in design was not being documented.
(4) Interface documents were not formally established to control the design review process.
(5) QA audits had not been completed to cover the design activities 1
at the site.
Due to these deficiencies, documented calculations for the support steel and load and location do not exist for a portion of the safety related 2" & under pipe hangers.
Approximately 543 piping subsystems are involved in this problem.
The existing review program has been more clearly documented to assure that the A-E reviews the installed hangers and performs calculations where
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Mr. James G. Keppler, Director October 8, 1980 Page 2 necessary to document the adequacy of the hangers.
The items noted by the NRC nave been corrected.
The Commonwealth Edison QA Dept.
has performed extensive audits in the area of design control anc review.
In addition, a surveillance program to monitor the continuing work has been instituted.
Although these proolems reflect upon the adequacy of the Quality Assurance program applicaDie to the small bore pipe hangers, it is judged based on the follow-up audits performed and the finoings uncovered and reported to the NRC, that the QA deficiencies to tne extent they exist were limited to the field design interface associated with small bore pipe hangers.
The corrective action discussed with the NRC (Region III) on August 29 and September 5, 1980 are expected to resolve these apparent deficiencies and *ill De the basis for closing this report under 10 CFR 50.55(e).
In this regard, the program for reporting progress on tne corrective action to be taken was discussed in the meeting witn your staf f on September 5, 1980.
It was subsequently agreed by Commonwealth Edison that periodic reports would be submitted to discuss the progress of the work.
As mandated by your Staff, these reports will be initiated two weeks af ter receipt of the formal NRC inspection report.
This inspection report has not been received as of the date of this letter.
Because the commitment to formal reporting of progress on corrective action has been documented in Item 3 of the Enclosure to Reference (a), no furhter reports under 10 CFR 50.55(e) are judgeo necessary.
This conclusion is supported by the fact that a comprehensive review of the subject def}ciencies has already been completed by your staf f and the primary purpose of the future reports is to provide a completion status.
If there are any further questions in this regard, please direct them to this office.
Very truly yours, L.
O. DelGeorge Nuclear Licensing Administrator l
LaSalle County Station LOD / rap cc:
Director of Inspection and Enforcement, DC l
RIII Inspector LSCS f
7259A l