ML20039E137
| ML20039E137 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/23/1981 |
| 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, NUDOCS 8201060572 | |
| Download: ML20039E137 (2) | |
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THE CLEVEL AND ELECTRIC iLLUMIN ATING COMPANY P.O. DoX 5000 e CLEVELAND. OHIO 44101 e TELEPHONE (216) 622 9800 e ILLllMINATING BLDG e 55 PUBLIC SOUARE "O
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Dalwyn R. Davidson
{CE, R December 23, 1981 SDEN 9,gEERING AND CONSTRUCTION D
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c Oh Mr. James G. Keppler Director, Region III 9
RECEIVED
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-D Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission p
IAN5 1982 *- C 799 Roosevelt Road U tcrit acg rygg N{pst E
Glen Ellyn, Illinois 60137
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Dear Mr. Keppler:
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Re: Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Incomplete Fill Detected in Reactor Building #2 Bioshield Wall (RDC 42(S1))
This letter serves as an Interim Report pursuant to 10CFR50.55(c) concerning incomplete fill of two cells in the Reactor Building #2 bioshield wall. This deficiency was first reported by E. Riley of The Cleveland Electric Illumina-ting Company to L. G. McGregor of your office on December 1, 1981.
This report includes a description of the deficiency, the methed of investiga-tion, and t~ne planned date for the Final Report.
Description of Deficiency Two cells were discovered to have been incompletely filled with heavyweight con-crete in the Reactor Building #2 bioshield wall. These areas were identified as a result of a radiation scan being conducted to evaluate the shielding capa-bilities of the bioshield wall. Two access holes were cut through the outer steel skin of the bioshield to permit visual inspection and the approximate dimensions of the voids were found to be 4' x 2' x 5' and 7' x 2' x 5'.
This deficiency was documented on Nonconformance Report P020-0258.
Method of Investigation This deficiency is being evaluated in conjunction with the evaluation currently being performed on the bioshield walls as discussed in our Interim Reports, RDC
- 34 (81), dated August 14, 1981, and December 18, 1981. A radiographic survey employing gamma spectrometry techniques is currently being used to investigate the possibility of additional similar anomalies in the bioshield concrete.
Cells with similar internal configuration as that of the subject cells are being scan-ned to establish their acceptability.
The results of the radiographic survey will be evaluated by Design Engineering.
DEC 3 0,1981 bo?N*ojffgga 48 WA?sy
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Mr. Janes G. Keppler December 23, 1981 Due to the extent of the evaluation and the limited accessability of Reactor Building f2 for the radiographic survey, the Final Report will be submitted to the NRC by June 18, 1982. The Final Report will include an analysis of the safety implication, the results of the evaluation and planned corrective actions.
Sincerely,
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auB2 Dalwyn R. Davidson Vice-President System Engineering and Construction DRD: bas cc: 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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