ML20039D301
| ML20039D301 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/18/1981 |
| 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, RDC-34(81), NUDOCS 8112310504 | |
| Download: ML20039D301 (2) | |
Text
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c THE CLEVEL AND ELECTRIC ILLUMIN ATING COMPANY P o. box 5000 m CLEVELAND. OHIO 44101 a TELEPHONE (216) 622-9800 m etLUMINATING DLDG e
55 PUBLfC SoVARE Dalwyn R. Davidson t1CE PRES: DENT SYSTEM ENGINEERING AND CONSTRUCTION December 18, 1981 Mr. James G. Keppler Director of Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE:
Perry Nuclear Power Plant Docket Nos. 50-440;50-441 Interim Report on Biological Shield Walls Heavy Density Concrete, Units 1 and 2
[RDC 34(81)]
Dear Mr. Keppler:
This letter serves as a second Interim Report in accordance with 10CFR50.55(e) concerning the heavyweight concrete in the Biological Shield Walls of both Reactor Buildings. The first Interim Report, submitted on August 14, 1981, indicated that the final report would be submitted to the NRC by December 18, 1981.
Mr. L. McGregor was informed on December 16, 1981, by Mr. G. LeidiclL TheClevelandElectricIlluminatingCompanythatasecondInterimReport%u.ld_t\\
be submitted in lieu of the final report, which will be submitted at J1ater N
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date.
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This report includes a description of the condition, testing meth 'and k
preliminaryevaluation,andtheplanneddateforthefinalreport.[
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~j Description of Deficiency
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Light, chalky material, up to three inches (3") thick, was observed at the top
/
s construction joints of the heavyweight bioshield concrete placements, for < n./
Reactor Building 1 - elevation 654' and for Reactor Building 2 - elevation 630'.
This material has a bulk specific gravity of approximately 75 pounds per cubic foot, rather than 195 pounds per cubic foot per the specified design requirement. Additionally, this material is soft enough to scratch with the fingernail and contains no ferrous aggregate.
Due to inaccessability, only three of twenty-four cells in Reactor Building 2 could be visually inspected for this material.
It could not be readily determined if this material ever existed at the top construction joints of any of the previous heavyweight placements.
8112310504 0
DEC 2 3198C MmA
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- MrvLJcmes G.. Keppler : : December 18, 1981 61' Testing Method and Preliminary Evaluation.
l J-jA radiographic survey employing gamma spectrometry techniques has been performed '
i at 89 locations for Unit I bioshield wall and 103 locations for Unit 2 bioshield
. wall.. Multiple measurements were ' taken at some. locations to bound areas of -
-reduced bioshield wall density.
y Unit 1 measurements indicated that normal wall / concrete densities were present at 75 of the 89 locations. Wall densities greater than normal were present at 3 locations, probably due. to increased steel _ thickness at these locations.
Reduced wall / concrete densities were present at the remaining 11 measurement locations. Estimated concrete densities range from 60 to 140 lbs. per cu. ft.
Unit 2 measurements indicated that normal wall / concrete densities at 90 of 103 locations. Wall densities greater than normal were found3at two locations.
Reduced wall / concrete densities in the range of 70 to 100 lbs.'per cu. ft.
were found at 5 locations.
The remaining 6 locatiens exhibited greatly reduced densities in the range of.10 to 100 lbs. per cu. ft..
GAI is presently carefully evaluating the shielding adequacy'of the bioshield
- wall in order to determine the need for further action.
In addition, the pattern, or lack thereof, for occurrence of reduced concrete density regions is being researched to indicate if similarities exist between Unit 1 and Unit 2.
Upon' completion of th'is evaluation, the Final Report will be filed to describe-the'results of the evaluation and'the planned corrective action.
Planned Pate for the Final Report ~
Due to the extent of this evaluation and the limited accessability of Reactor Building #2, the Final Report will be submitted to the NRC by June 4,1982.
The Final Report will describe the results of our evaluation and the planned 1 corrective actions.
Very truly yours, W
fY Dalwyn R. Davidso Vice President System Engineering and Construction DRD:pab cc: NRC Site Office Director Office of Inspection and Enforcement et U.S. Nuclear Regulatory Commission Washington, D.C.
20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.
20555
.