ML20129J567

Insp Rept 50-458/85-42 on 850603-07.Violation Noted:Failure to Tag Lifted Leads in Panel 821 in Main Control Room

ML20129J567
Person / Time
Site:	River Bend
Issue date:	07/17/1985
From:	Bennett W, Craig Harbuck, Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20129J558	List: ML20129J555 ML20129J562 ML20129J567
References
50-458-85-42, NUDOCS 8507230135
Download: ML20129J567 (3)

See also: IR 05000458/1985042

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APPENDIX B

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/85-42 CP: CPPR-145

Docket: 50-458

Licensee: Gulf States Utilities

P. O. Box 2951

Beaumont, Texas 77704

Facility Name: River Bend Station

Inspection At: River Bend Site, St. Francisville Louisiana

Inspection Conducted: June 3-7, 1985

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. Inspectors:

W. R. Bennett, Reactor Inspector

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Date

Project Section A, Reactor Project Branch 1

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C. C. Harbuck, Reactor Ifispector Date

Project Section A, Reactor P ect Branch 1

Approved: _, // // /e 9 /7 f(

J./ P./ Jau nT Chief, Project Section A, Da t'e /

Rdactor roject Branch 1

Inspection Summary

Inspection Conducted June 3-7,1985(Report 50-458/85-42)

Areas Inspected: Routine unannounced inspection of preoperational test

witnessing and preoperational test results evaluation. The inspection involved

56 inspector-hours onsite by two NRC inspectors.

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Results: Within the two areas inspected, one violation was identified

(Failure to tag lifted leads, paragraph 2).

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DETAILS

1. Persons Contacted

Gulf States Utilities (GSU)

• D. L. Andrews, Director of Training

• T. P. Anthony, Senior Mechanical Engineer

• C. L. Ballard, Projects Supervisor

• J. Bleau, Radwaste Specialist .

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• J. F. Booker, Manager - Engineering, Fuels, and Licensing

• W. J. Cahill, Senior Vice President

• L. Campo, Radwaste Specialist

L *T.L.Crouse, Manager-QualityAssurance(QA)

• P. J. Dautel, Licensing Staff Assistant

• J. C. Deddens, Vice President

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D. R. Derbonne, Preoperations Testing Supervisor

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• R. Easlick, Radwaste Supervisor

• L. A. England, Supervisor - Licensing

• P. E. Freehill, Superintendent Startup and Test (SU&T)

j *D. R. Gipson, Assistant Plant Manager

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• K. C. Hodges System QA Supervisor

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D. Jernigan, SU&T Engineer

l *G. R. Kimmell, Supervisor Operations QA

l *G. V.' King, Plant Services Supervisor

• M. Lett,' Radiation Protection /Radwaste

T. Pao, SU&T Engineer

, *T. F. Plunkett, Plant Manager

i *S. R. Radebaugh, Assistant Superintendent SU&T

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• D. M. Reynerson, Executive Assistant

• C. Rohrmann, Technical Training Coordinator

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• J. E. Spivey, QA Engineer

• R. B. Stafford, Director Quality Services

K. E. Suhrke, Manager Project Planning and Coordination

• P.. F. Tomlinson, Director Operations QA

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Other Contractor Contacts

K. Bullen, General Electric SU&T Engineer

• F. W. Finger, Stone & Webster (SWEC) Project Manager, Preliminary Test

Organization

~*B. R. Hall, SWEC Assistant Superintendent Field Quality Control

The NRC inspectors also contacted other site personnel including

administrative, clerical, operations, testing, and inspection personnel.

• Denotes those attending the exit interview on June 7, 1985.

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2. Preoperational Test Witnessing

The objective of this portion of the inspection was to verify that

testing is conducted in accordance with approved procedures. The NRC

inspectors observed performance of portions of 1-PT-508, " Reactor

Protection System Preoperational Test," and 1-PT-200, " Remote Shutdown

System Preoperational Test." The testing was performed and documented in

accordance with approved procedures.

During observation of 1-PT-508, the NRC inspector found four leads in

panel 821 which were lif ted without having temporary alteration tags as

required by River Bend Procedure TI-17, " Test Controls" Revision 8,

January 18, 1985. Further investigation determined that the leads had

been lifted for several days. This is an apparent violation (458/8542-01).

In addition to the aforementioned leads, several other leads were not

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landed and the NRC inspector could not determine whether they were lifted

leads or spare leads. Discussions with several licensee personnel in the

area did not disclose the purpose of the leads. Subsequent investigation

by the licensee determined that all suspect leads were spares. The

licensee determined that a means of identifying spare leads was needed and

, committed to the NRC inspector to develop and implement a means of spare

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lead identification. This is considered an open item (458/8542-02).

No other violations or deviations were identified in this portion of the

inspection.

3. Preoperational Test Results Evaluation

The objective of this portion of the inspection was to assure that the

licensee is performing an adequate evaluation of test results and to

assure that all test data is either within acceptance criteria or that

deviations are properly dispositioned. The NRC inspector reviewed

completed preoperational test procedure 1-PT-210 " Integrated Emergency

Core Cooling System and Loss of Offsite Power." The NRC inspector

discovered several minor documentation problems which were corrected by

the licensee. One test exception was outstanding and was properly

documented. All test exceptions reviewed by the NRC inspector were

properly dispositioned and documented.

No violations or deviations were identified in this portion of the

inspection.

4. Exit Interview

l An exit interview was conducted on June 7, 1985, with those personnel

j denoted in paragraph 1 of this report. At this exit interview the NRC

l inspectors summarized the scope and findings of this inspection.

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