GO2-83-654, Interim Deficiency Rept Item 221 & Final Deficiency Rept Item 251 Re Namco EA180 & EA740 Limit Switches & Limitorque Motor Operators W/Motors from Baldor Electric Co, Respectively.Initially Reported on 830104 & 0422

Interim Deficiency Rept Item 221 & Final Deficiency Rept Item 251 Re Namco EA180 & EA740 Limit Switches & Limitorque Motor Operators W/Motors from Baldor Electric Co, Respectively.Initially Reported on 830104 & 0422

ML20077F749
Person / Time
Site:	Columbia
Issue date:	07/25/1983
From:	Carlisle C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, GO2-83-654, NUDOCS 8308030023
Download: ML20077F749 (3)

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Washington Public Power Supply System P.O. Box 968 3000GeorgeWashingtonWay Richland, Washington 99352y8 (809ga,72-5000 Docket No. 50-397 E// /2: 3a, July 25, 1983 J/4;.,

G02-83-654 Mr. J. B. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596

Subject:

10CFR50.55(e) CONDITIONS: #221, NAMC0 EA180 AND EA740 LIMIT SWITCHES; AND #251, LIMITORQUE MOTOR OPERATORS WITH MOTORS FROM BALD 0R ELECTRIC COMPANY

Reference:

1) Telecon QA2-83-003, dated January 4, 1983, L.C. Floyd to J. Elin.

2) Telecon QA2-83-059, dated April 22, 1983, L.C. Floyd to R. Dodds.

In accordance with the provisions of 10CFR50.55(e), your office was informed by telephone, of the above subject conditions. Attachment I provides the Project's final report on non-reportable Condition #221. Attachment II provides our interim report on Condition #251. We will continue to provide your office with quarterly updates on Condition #251 until resolved.

The next report will be provided by October 21, 1983.

If you have any questions, contact Roger Johnson, WNP-2 Project QA Manager, at (509) 377-2501, extension 2712.

C. S. Carlisle Program Director, WNP-2 LCF/kd Attachments: (2) As stated cc: W.S. Chin, BPA N.D. Lewis, EFSEC A. Toth, NRC Resident Inspector Document Control Desk, NRC 8308030023 830725 PDR ADOCK 05000397 s PDR 1

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Attachment I WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 DOCKET NO. 50-397 LICENSE NO. CPPR-93 10CFR50.55(e) CONDITI0ii J221 NAMC0 EA180 AND EA740 LIMIT SWITCHES Final Report Description of Deficiency The Project was informed via a 10CFR50.55(e)/Part 21 report to the NRC Region II by the Bechtel Power Corporation (involved with the construction of the Grand Gulf Nuclear Unit) that NAMCO EA740 limit switches which did not have specific manufacturing codes may be produced containing materials not traceable to the

-Equipment Environment Qualification Report.

Safety Implications The Project's initial review identified two limit switches (SGT-POS-V/2A and SGT-POS-V/28) used to indicate the position (open/ closed) of safety-related valves in the standby gas treatment system, to which the Part 21 was applicable.

Failure of the limit switches would result in erroneous position indication, and would consequently be a violation of Regulatory Guide 1.4.7, Bypass and Inoperable Status Indication.

Corrective Action The Equipment Qualification Group, through direct contact with NAMC0 Controls, has acquired documentation which establishes what materials were used in the identified NAMC0 switches of concern. An engineering comparative evaluation was performed which documents the similarity between older NAMCO EA180 and EA740 switches and the prototype which was tested and qualified. This has established the applicability of the acceptable qualification testing to the switches of concern, therefore, the switches have been determined to be qualified.

The conclusion is that the Part 21 report on EA740 NAMCO limit switches is not applicable to WNP-2 and therefore, the condition is not reportable under the criteria for a 10CFR50.55(e) report.

Cause for the Deficiency The Part 21 was filed in the belief the materials used in certain limit switches could not be documented applicable to the qualification report.

Action to Prevent Recurrence The vendor has primary responsibility for assuring that components supplied correlate with the qualification records subraitted to substantiate their suita-bility for the service designated.

The Supply System Equipment Qualification Program represents a complete review of safety-related equipment relative to environmental and seismic qualification.

This program assures that components are qualified for their design service i conditions and will preclude unqualified components in completed plant instal-lations, unless justified by specific evaluation, such as the JIO.

. .4 k Attachment II WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT N0. 2 MCKET N0. 50-397 LILtriSE NO. CPPR-93 10CFR50.55(e) CONDITION #251 LIMITORQUE MOTOR OPERATORS WITH MOTORS FROM BALD 0R ELECTRIC COMPANY Interim Report Description of Deficiency Motor operated valves were received from the manufacturer with unqualified motors by Baldor Electric Cocapany. Condition was discovered after valves were instal-led during equipment qualification group walkdown to obtain nameplate data on March 24, 1983. The valves involved are SW-M0-187A, -187B, -188A, and -188B.

Safety Significance Valves SW-110-187A and B and SW-M0-188A and B are Service Water System (SW) iso-lation valves at the interface with the Reactor Closed Cooling Water System (RCC) to provide an alternate cooling water source for the fuel pool cooling heat exchangers FPC-HX-lA and 18. The valves will allow utilization of the Seismic Class I service water system for FPC cooling in the event of an earth-quake. Operation of the valves is not required for normal plant operations, but only under emergency conditions. The unqualified motors would have the -

potential for jeopardizing corrective action to meet emergency conditions and the deficiency is, therefore, considered reportable.

Cause for the Deficiency Error on the part of the manufacturer in that Limitorque supplied motor opera-tors to WMP-2 with motors that were not qualified to IEEE 382 - 1972.

Corrective Action The nanufacturer, Limitorque, has been nade aware that the motors were impro-perly supplied and is to replace the existing motors with units qualified to IEEE-382-1972 meeting requirements of NUREG-0588 Category II. Startup Defici-ency Reports (SDR) #8308, 8309, 8310, and 8312 have been issued to identify the deficient condition. The physical replacement of the motor operators has been deferred until the first refueling outage. This decision is based on the 4 service water valves identified are part of the fuel pool cooling modifica-tion, which has been deferred.

Action to Prevent Recurrence The vendor has primary responsibility for assuring that components supplied correlate with the qualification records submitted to substantiate their suita-bility for the service designated.

The Supply System Equipment Qualification Program represents a complete review of safety-related equipment relative to environmental and seismic qualification.

This program assures that components are qualified for their design service conditions and will preclude unqualified components in completed plant instal-lations, unless justified by specific evaluation, such as the J10.