ML20080N566

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Forwards Drywell Coating Evaluation, Technical Data Rept, Per SEP Topic VI-1, Organic Matls & Post-Accident Chemistry
ML20080N566
Person / Time
Site: Oyster Creek
Issue date: 02/10/1984
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML20080N569 List:
References
TASK-06-01, TASK-6-1, TASK-RR NUDOCS 8402220286
Download: ML20080N566 (2)


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GPU Nuclear Corporation

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Parsippany, New Jersey 07054 201 263 6500 TELEX 136-482 Wnter's Direct Dial Number:

February 10, 1984 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Crutchfield:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 SEP Topic No. VI-1 Organic Materials and Postaccident Chemistry During the integrated assessment of the subject SEP topic, the NRC staff requested GPUN representatives to inspect the drywell and torus interiors to determine their condition and coating materials. The safety objective of this topic is to ensure that protective coatings inside the drywell and torus do not consist of material that would decompose in radiation environments and potentially foul pump seals, bearings, or cooling passages; create a hazardous environment; or cause material failures.

Inspection of the drywell and torus interiors were conducted during the current Cycle 10 refueling outage. The attached report entitled "Drywell Coating Evaluation" provides detailed description of the drywell inspection and the results. As indicated in the report, the drywell coating was inspected by performing visual, adhesion and coating thickness measurements.

It was concluded that the drywell coating is in satisfactory condition and does not require repairs at this time. GPUN plans to reinspect the drywell interior walls during the next refueling outage.

Torus interior is being ccated with epoxy (Mobil 78 Series) during the current refueling outage.

Behavior of the coating material under the design basis accident (DBA) condition and application of the material were evaluated.

It was concluded that the material and coating procedure meet the intent of 8402220286 840210 PDR ADOCK 05000219 e

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h GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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. the requirements set forth by American National Standards Institute (ANSI) standard No. N101.2.

Very truly yours, ge _ s.

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P.

B.'

riedler Vice President and Director Oyster Creek 1r cc: Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.

19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N. J. 08731 1