ML20093A252

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Final Deficiency Rept (Rdc 100(84)) Re Phase III Limitorque Actuator Rework Program.Initially Reported on 840316. Limitorque Actuators Corrected in Accordance W/Provisions of Special Project Plan 1607
ML20093A252
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 06/29/1984
From: Edelman M
CLEVELAND ELECTRIC ILLUMINATING CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
(RDC-100(84)), NUDOCS 8407100253
Download: ML20093A252 (2)


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CLEV" LAND. oHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BloG. - 55 PUBLICSOUARE U'

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Serv:ng The Best Location in the Nation MURRAY R. EDELMAN VICE NESIDENT NUCU A R Mr. James G. Keppler Regional Administrator, 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 Numerous Deficiencies Associated With Limitorque MOV Actuators

[RDC 100(84)]

Dear Mr. Keppler:

This letter serves as th, final report pursuant to 10CFR50.55(e) relative to deficiencies detected during the Phase III Limitorque Actuator Rework Program conducted at PNPP.

Mr. R. Knop of your of fice was firs t notified on March 16, 1984, by Mr. E. Riley of The Cleveland Electric Illuminating Company (CEI) that preliminary results of the rework program in progress revealed numerous deficiencies which were being evaluated.

Previously we submitted an interim report on April 12, 1984.

This report contains a description of the deficiency, an analysis of safety implications and the corrective action taken.

Description of Deficiency The Cleveland Electric Illuminating Co. (CEI) and Gilbert / Commonwealth Inc.

(C/C Inc.) developed a program to rework safety-related Limitorque actuators with the objective of satisfying equipment qualification requirements and providing maximum operating reliability.

Ti a program was completed in three (3) phases with Phase I consisting of a walkdown to obtain all qualification data and identify any obvious deficiencies.

Phase II involved evaluating the results and developing rework procedures and Phase III consisted of the actual disassembly, rework and re-assembly of the actuators.

During the performance of Phase III for Unit 1 and Common, an interim trend analysis was conducted on required rework actions and identified equipment / material deficiencies such as damaged wiring, inadequate crimping, cracked limit-switch rotors and missing / damaged mechanical parts.

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pr.JrmesG.Kappler June 29, 1984 Analysis of Safety implication Due to the nature and number of Identified actuator deficiencies, it was postulated that some actuators may have been prevented from operating. As t

these actuators are used in several systems essential to safe shutdown of the reactor, one or more of these systems may have been precluded from operating.

Any other corrections of the operators included in our preliminary evaluation which were due to desired engineering changes, normal maintenance items or attributable to the actual rework program itself have now been determined not to be subject to reportability evaluation.

Corrective Action Taken j

Deficiencies related to Unit 1 and Common Limitorque MOV actuators have been corrected in accordance with the provisions of Special Project Plan (SPP) 1607, " Procedure for Rework of Saf e ty-Related Limitorque Actuators", excep t for four actuators in the N11 system, which will be replaced in their entirety and any new work that is resulting from ongoing construction activities.

New/ replacement actuators for Unit I and Common will be reworked in accordance with.SPP 1607.

In addition, to assure the acceptability of spare and replace-ment parts, manufacturing surveillance by Gilbert / Commonwealth Inc. Inspection personnel was initiated at Limitorque's Lynchburg, Virginia facility.

Reinspection and required correction of the Unit 2 MOV actuators will be tracked on Nonconformance Report 0QC-0782 based upon their indeterminate status. Resolution of this nonconformance report will be completed as indi-cated by the Unit 2 construction schedule.

Please call if there are any additional questions.

Sincerely, k ~f f 4$ Y 4

Murray R. Edelman Vice President Nuclear Group MRE:pab cc:

Mr. J. A. Grobe NRC Site Office Director Office of Inspection and Enforcement i

U.S. Nuclear Regulatory Commission Washington, D.C.

20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Woohington, D.C.

20555 Records Center, SEE-IN Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 P

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