ML20203G032

Documents Util Actions Re IE Info Notice 86-003 Concerning Potential Deficiencies in Environ Qualification of Limitorque Wiring,In Response to 860718 Discussions.Insp Delayed Until Fall 1986 Refueling Outage

ML20203G032
Person / Time
Site:	Cooper
Issue date:	07/21/1986
From:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
To:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CNSS860575, IEIN-86-003, NUDOCS 8607310237
Download: ML20203G032 (2)

Text

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COOPER NUCLEAR STATION

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July 21, 1986

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• Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Subject:

Inspection of Limitorque Operators

Reference:

1) IE Information Notice 86-03

2) Military Standard, MIL-STD-105D, Sampling Procedures and Tables for Inspection by Attributes

Dear Mr. Martin:

This letter is in response to discussions between members of your staff and NPPD corporate and site management on July 18, 1986. This letter will document the District's actions to date regarding Reference 1 and our agreed upon plan of action.

Reference 1 identified potential deficiencies in the environmental qualification of internal Lititorque motor operator wiring. The Notice described licensee and manufacturer concerns with being able to identify and subsequently prove qualification of the internal wiring. Of particular concern was the replace-ment of Limitorque supplied wiring or additions made by licensees.

Prior to the issuance of Reference 1, the District conducted an inspection of the applicable Limitorque operators located inside the primary containment.

These operators were inspected with regard to motor insulation, wiring, terminal blocks, T-drains, torque switch settings, etc. No deficiencies were

identified.

Following receipt of IE Information Notice 86-03, the District prepared a Special Test Procedure (STP) to inspect the balance of those Limitorque valve operators subject to the requirements of 10CFR50.49. Since these operators are located outside the drywell, most of them could be inspected at power.

However, this inspection would necessitate voluntarily entering the LCOs associated with ECCS systems and, hence, reduces the number of safety systems available to ensure the safe operation of the plant. Additionally, high radiation in certain areas would result in significant radiation exposure to craft and engineering personnel if the inspections were conducted at power.

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Mr. Robart D. Martin July 21, 1986 Page 2 Based upon (1) the results of the inspection of the operators in the drywell and (2) the hazards described above, the District determined that the proper course of action would be to delay the inspection to the Fall 1986 refueling outage or any unscheduled outage.

On the other hand, members of your staff have indicated that other licensees have completed inspections of their Limitorque operators and have invariably found potential deficiencies. Based upon this information, the District has agreed to perform the aforementioned inspection while at power. In performing this inspection, sampling techniques will be utilized. The sample size will be based upon the guidance provided by Reference 2. The actual inspection will be conducted in accordance with CNS STP 86-02 and if any deficiencies are discovered, they will be corrected per CNS Equipment Specification Change (ESC)86-016. Region IV vill be kept informed as to Cooper's progress and findings.

If you have any additional questions regarding this matter, please contact myself or Mr. Guy Horn at Cooper Station.

Sincerely,

/y AaM~

J. M. P11 ant Technical Staff Manager Nuclear Power Group I JMP:KCW:1b

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