ML20199F193

Insp Rept 50-285/86-16 on 860527-29.Violation Noted:Failure to Establish Measures to Prevent Acceptance of Electrical Cable W/Insufficient Matl Test Rept

ML20199F193
Person / Time
Site:	Fort Calhoun
Issue date:	06/17/1986
From:	Ireland R, Norman D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20199F177	List: ML20199F174 ML20199F188 ML20199F193
References
50-285-86-16, IEIN-83-72, IEIN-86-003, IEIN-86-3, NUDOCS 8606240220
Download: ML20199F193 (4)

See also: IR 05000285/1986016

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APPENDIX B

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report:

50-285/86-16

Operating License:

DPR-40

Docket: 50-285

Licensee: Omaha Public Power District

1623 Harney Street

Omaha, Nebraska 68102

Facility Name:

Fort Calhoun Station, Unit 1

Inspection At: Omaha and Fort Calhoun, Nebraska

Inspection Conducted: May 27-29, 1986

Inspector:

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D. E. Norman, Reactor Inspector, Engineering

Date

Section, Reactor Safety Branch

Approved:

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R. E. Ireland, Chief Engineering Section,

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Reactor Safety Branch

Inspection Summary

Inspection Conducted May 27-29, 1986 (Report 50-485/86-16)

Areas Inspected:

Special, announced inspection to determine what wiring was

installed in Limitorque valve operators and to review licensee's environmental

equipment documentation to ensure that qualification of wiring was adequately

established. The inspection also included a review of licensee's actions

relative to Information Notices (IN) 83-72 and 86-03.

Results: The inspection determined that the licensee had replaced wiring in

Limitorque valve operators with wiring which was qualified to the requirements

of 10 CFR 50.49; however, the NRC inspector found that the licensee had

accepted safety-related wiring with a material test report which did not

document results of all required tests.

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DETAILS

1.

Persons Contacted

Omaha Public Power District (0 PPD)

J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs

• D. J. Munderloh, Sr. Engineer, Nuclear Regulatory and Industry Affairs

• M. R. Core, Supervisor, Maintenance FCS

A. W. Richard, Manager, Quality Assurance

• T. L. Patterson, Manager, Technical Support

R. Ronning, Co-op Engineer

• J. Tucker, Senior Electrical Engineer, GSE

• R. L. Jaworski, Section Manager, Technical Services

• J. K. Gasper, Manager, Administrative Services

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• R. L. Andrews, Division Manager, Nuclear Production

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• H. Faulhaber, Manager, Electrical Engineering, GSE

• S. K. Gambhir, Section Manager, GSE

R. Conner, Electrical Engineer, Maintenance

1

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NRC

• D. E. Norman, Reactor Inspector

• Denotes those present at the exit interview.

2.

Purpose

The purpose of this inspection was to identify wiring used in Limitorque

valve operators installed in a harsh environment, to review licensee's

environmental qualification documentation to ensure that qualification of

wiring was adequately established, and to review licensee's actions

relative to ins 83-72 and 86-03.

3.

Inspection Summary

a.

Review of Previous Licensee Actions

As a result of notices from industry and the NRC, the licensee had

performed various inspections and in some instances modifications to

Limitorque valve operators located in a harsh environment. During

the last outage, internal wiring in each operator was removed and

replaced with Rockbestos Firewall III wiring.

During this same

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inspection, terminal blocks and splices were inspected and modified

as required to be upgraded to a qualified status.

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b.

Hardware' Inspection

The EQ master list contained 28 Limitorque operators, with 21 inside

containment and 7 outside. The following three operators, located

outside containment were inspected by the NRC inspector for proper

wiring, terminal blocks, splices, and switches.

o

HCV-308 (S/N - N/A)

o

HCV-347 (S/N 100847)

o

HCV-1384 (S/N 130436)

Gray and tan wires were found during the inspection, but none of the

wires had manufacturer identification markings.

It was explained by

the licensee that the wires had been removed from a reel of

3-conductor jacketed Firewall III cable which had the identification

on the jacket; therefore, the insulation had not been marked,

c.

Documentation Review

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Supporting qualification documentation for Limitorque operators was

included in Operations Support Analysis Report (0SAR) 85-17. The

following items from the OSAR were reviewed by the NRC inspector:

(1) System Component Evaluation Work (SCEW) Sheets: SCEW sheets for

all operators were reviewed to determine specified and

qualified environmental conditions, method of qualification,

qualified life, and reports used to support qualification.

No

questions were identified with the SCEW sheets.

(2) Vendor / Consultant Qualification and Analysis Reports: The NRC

inspector verified qualification of Limitorque operators by

reviewing Limitorque test report B0058 dated January 11, 1980,

and supporting analyses conducted by Di Benedetto Associates as

reported in Document Number OPD03-07-06 dated April 19, 1985.

These documents support a 40-year life for the operators when

certain qualified age sensitive materials (i.e., motor coil

insulation, switch base and rotor material, terminal blocks, and

wire insulation) are installed as tested.

(3) Limitorque Operator Modification Documentation: The following

documentation which addressed the inspection and modification of

operators was reviewed by the NRC inspector:

o

Engineering Evaluation and Assistance Request (EEAR) dated

December 23, 1985

o

Safety-Related Design Change Order (SRDCO) 85-17, dated

December 28, 1986

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Work Instruction MR-FC-85-220

Instructions.in MR-FC-85-220 were used by the licensee for the

inspection and modification of operator wiring, terminal blocks,

and splices. Records showed that splices and terminal blocks

were modified as required and all internal wiring was replaced

with Firewall III wiring purchased under Purchase Order 526016,

dated April 21, 1982, to OPPD Specification GSEE-0504. Quality

Control verified that the designated wire was installed in each

operator.

(4) Wire Purchase Order and Certified Test Report

Purchase Order 526016 was reviewed and appeared to adequately

describe requirements for wire to be used in a harsh

environment. The Rockbestos material test report for the cable,

however, neither described the cable as Firewall III nor

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reported radiation aging of the cable as required by the

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purchase order. The cable was subsequently accepted by 0 PPD

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receiving and placed in CQE stores where it could be used in a

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harsh environment. The failure to adequately control purchase

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material is a violation of 10 CFR 50, Appendix B (285/8616-01).

Based on available documentation tne NRC inspector was unable to

verify that the cable had been radiation aged and was Firewall

cable which had been qualified by Rockbestos Report

Number QR-4802. On May 29, 1986, a telephone call by the

licensee confirmed that the cable (Product Code C07-3133) was

Firewall III with irradiated XLP insulation.

It was, therefore,

qualified for use in the operators.

4.

Exit Meeting

An exit meeting was conducted on May 29 with the persons identified in

paragraph 1 at which time results of the inspection were discussed.

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