ML20044C447

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Forwards Insp Repts 50-498/93-08 & 50-499/93-08 on 930217- 19.Apparent Violations Noted But Not Cited.Violations Involved TS 3.5.2,failure to Take Corrective Actions Following Failure of Valve & Operability Determinations
ML20044C447
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 03/17/1993
From: Collins S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Hall D
HOUSTON LIGHTING & POWER CO.
Shared Package
ML20044C448 List:
References
NUDOCS 9303230048
Download: ML20044C447 (5)


See also: IR 05000498/1993008

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611 RYAN PLAZA DRIVE, SUITE 400

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ARLINGTON, TEXAS 76011-8064

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MAR l T 1993

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Dockets: 50-498

50-499

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Licenses: NPF-76

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Houston Lighting & Power Company

ATTN: Donald P. Hall, Group

Vice President, Nuclear

P.O. Box 1700

Houston, Texas 77251

SUBJECT:

NRC INSPECTION REPORT 50-498/93-08; 50-499/93-08

This refers to the inspection conducted by Mr. H. Runyan of this office on

February 17-19 and 23-26, 1993. The inspection included a review of

activities authorized for your South Texas-Project, Units 1 and 2, facility.

At the conclusion of the inspection, the findings were discussed with you and

those members of your staff identified in the enclosed report.

The inspection focused on issues associated with recent problems that had

developed in your program for the testing and maintenance of motor-operated

valves. Within this area, the. inspection consisted of selective examinations

of procedures and representative records, interviews with personnel, and

observation of activities in progress.

Three apparent violations were identified and are being considered for

escalated enforcement action in accordance with the " General Statement of

Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy),

10 CFR 2 Appendix C (1992). Accordingly, no Notice of Violation is presently -

being issued for these inspections findings.

Please be advised that the

number and characterization of the apparent violations described in the

enclosed inspection report may change as a result of further NRC review.

The first apparent violation involved operation of Unit 2 in violation of

Technical Specification 3.5.2.

During the period of April 1989.to October

1990, the Train A low head safety injection isolation valve to reactor coolant

system cold leg, SI-31A, was inoperable.

Following a loss of coolant

accident, this condition would have prevented a transfer to hot leg

recirculation as assumed in the safety analysis.

The second apparent violation involved the failure to take corrective actions

in accordance with 10 CFR 50, Appendix B, Criterion XVI, following the initial

failure of valve SI-31A, which subsequently led to a recent failure of the

same valve under apparently identical circumstances.

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The third apparent violation involved the apparent failure to perform a proper

operability determination of five residual heat removal system (RHR) suction

isolation motor-operated valves that were operated with torque loadings in

excess of the vendor qualified rating. The initial corrective action response

to this issue appeared contrary to 10 CFR 50, Appendix 8, Criterion XVI. This

apparent violation was similar to a previous violation issued in NRC

Inspection Report 50-498/92-06; 50-499/92-06, which involved motor-operated

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valves that were receiving excessive applications of thrust.

An enforcement conference to discuss these apparent violations has been

scheduled for March 25, 1993. The purposes of this conference are to discuss

the apparent violations, their cause and safety significance; to provide you

the opportunity to point out any errors in our inspection report; to provide

an opportunity for you to present your proposed corrective actions; and to

discuss any other information that will help us determine the appropriate

enforcement action in accordance with the Enforcement Policy.

In particular,

we would like for you to address at the conference why the problems with

Motor-0perated Valve SI-31A were not identified and as a result, the valve was

not repaired for a period of 18 months. Also, please provide further

justification for lowering the maximum expected differential pressure for the

RHR suction isolation valves, and explain what actions wili be taken to assure

the long-term operability of the RHR suction isolation valves. You will be

advised by separate correspondence of the results of our deliberations on

these matters. No response regarding these apparent violations is required at

this time.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of

this letter and its enclosure will be placed in the NRC Public Document Room.

Should you have any questions concerning this inspection, we will be pleased

to discuss them with you.

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Samuel J. Co lins, Director

Division of eactor Safety

Enclosure:

Appendix - NRC Inspection Report

50-498/93-08 w/ Attachment

50-499/93-08 w/ Attachment

cc w/ enclosure:

Houston Lighting & Power Company

ATTN: William J. Jump, Manager

Nuclear Licensing

P.O. Box 289

Wadsworth, Texas 77483

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City of. Austin

Electric. Utility Department

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ATTN:

J. C. Lanier/M. B. Lee

P.O. Box 1088

Austin, Texas 78767

City Public Service Board.

ATTN:

R. J. Costello/M. T. Hardt

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P.O. Box 1771

San Antonio, Texas 78296

Newman & Holtzinger, P. C.

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ATTN: Jack R. Newman, Esq.

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1615'l Street, NW

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Washington, D.C.

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ATTN:

D. E. Ward /T. M. Puckett

P.O. Box 2121

Corpus Christi, Texas 78403

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Records Center

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Mr. Joseph M. Hendrie.

50 Be11 port Lane

Be11 port, New York 11713

Bureau of Radiation Control

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1101 West'49th Street

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Austin, Texas 78756

Judge, Matagorda County

Matagorda County Courthouse

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Licensing Representative

Houston Lighting'& Power Company

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