ML20058F075
| ML20058F075 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/23/1982 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, RDC-47(82), NUDOCS 8207300284 | |
| Download: ML20058F075 (3) | |
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THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P O BOX 5000 m CLEVELAND, OHIO 44101 e TELEPHONE (216) 622-9800 m ILLUMINATING BLOG e 55 PUBLIC SOUARE yg Serving The Best Location in the Nation D;lwyn R. Davidson VICE PF EStDENT SYSTE M E NGINEERING AND CONSTRUCTION July 23, 1982 Mr. James C. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory CommissLon 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE:
Perry Nuclear Power Plant Docke t Nos. 50-440; 50-441 Final Report Concerning Deficient Code Data Reports
[RDC 47(82)]
Dear Mr. Keppler:
This letter serves as a final report pursuant to 10CFR50.55(e) and provides the status of our evaluation of inadequate Code Data Reports submitted by various manufacturers for equipment supplied to the Perry Nuclear Power Project.
Initial notification that these deficiencies were being evaluated by The Cleveland Electric Illuminating Company (CEI) was made to your office on February 23, 1982, by Mr. R. L. Vondrasek of CEI. Our interim report on this subject was submitted to your office on March 23, 1982, by CEI.
Description of Defletency The following identified deficiencies reflect the inadequacies of the submitted Code Data Reports:
1)
Not all nozzles (and/or their sizes) listed.
2)
Improper and missing references for bolting materials.
3)
Incorrect side of head to pressure (convex or concave) specifled.
4)
Incorrect size for instrument taps specified.
These deftclencies represent discrepancies between the equipment, designed in accordance with ASME Code,Section III, and the Code Data Reports supplied by the manufacturer.
tLQ '0 F207300284 820723 L
PDR ADOCK 05000440 S
PDR gg7
Mr. Jzmes G. Ksppler July 23, 1982 Evaluation Results Upon identification of the problem, meetings were held with the installing contractor, Perry Nuclear Power Plant personnel, and the National Board of Boiler and Pressure Vessel Inspectors and concurrence was obtained by all parties on the requirements of ASME,Section III (NCA 8300 and 8400) for Code Data Report content. Based on these agreed upon clarifications, a survey was conducted by the Perry Project on a representative sample of ASME Code Data Reports. The sample included a Code Data Report for a typical piece of each type of equipment (e.g., tank, pump, compressors, etc.) from each vendor supplying Code equipment. This survey consisted of -a comparison of the Code Data Report with the design drawing and a visual inspection of the equipment was then performed as appropriate to verify the results of each comparison.
As a result of this survey, we have concluded that:
1.
Most of the discrepancies identified were minor in nature.
In all cases reviewed, the information necessary for making the Code Data Reports complete and accurate was found rc Le available on site.
Information not listed on the data reports was contained in the applicable design drawing and supporting documentation ;i.e., Certified Material Test Report, e tc.).
2.
All the Code Data Reports had originally been accepted by an Authorized Nuclear Inspection Agency. The majority of discrepancies have been determined to be the result of variance in the interpretation of code requirements.
3.
The vast majority of discrepancies identified pertained to N-1, N-1A, and N-6 forms submitted for pressure vessels and storage tanks. Of these Code Data Report discrepancies, none involved any equipment defects.
None of the Code Data Report corrections involved equipment changes.
4 The only changes required were the correction of several Code Data Reports. No material or equipment modifications were required.
Based on these conclusions, we feel that the items were built correctly to the requirements of ASME,Section III, and the discrepancies noted on the Code Data Reports do not represent a significant deficiency.
Corrective Action Those Code Data Reports which were determined to be deficient were returned to the manufacturer for correction and most have been returned to PNPP. The National Board of Boller and Pressure Vessel Inspectors has been asked to assist some vendors in making the remaining Code Data Report corrections. The Perry Nuclear Power Project will also recommend to the ASME and inspection i
Mr. Jam:s G. Keppler July 23, 1982 agencies that more clarification of the requirements be prov1ded for completing Code Data Reports. Review of Code Data Reports prior to Installation will continue and any discrepancies will' be documented and handled on a case-by-case basts.
If there are any questions, please do not hesitate to call.
Si cerely o
D. R. Davidson Vice President System EngLneering and Construction DRD:pab cc:
Mr. M. L. Gildner NRC Site Office Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.
20555
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