IR 05000458/1993028
| ML20059G988 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 01/14/1994 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20059G974 | List: |
| References | |
| 50-458-93-28, NUDOCS 9401260128 | |
| Download: ML20059G988 (2) | |
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APPENDIX B j
U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
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Inspection Report:
50-458/93-28
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Operating License:
NPF-47 Licensee:
Gulf States Utilities P.O. Box 220 i
St. Francisville, Louisiana 70775-0220
.i Facility Name: River Bend Station Inspection At:
St. Francisville, Louisiana
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i Inspection Conducted:
November 7 through December 18, 1993 Inspectors:
W. F. Smith, Senior Resident Inspector C. E. Skinner, Resident Inspector in Training
P. C. Wagner, Team Leader, Division of Reactor Safety
. L a, Reactor Engineer, Division of Reactor Safety, Region II
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Approved:
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'LE.pagliardo, Chief,ProjectSectionC Datel Inspection Summary
Areas Inspected:
Routine, unannounced inspection of plant status, onsite response to events, operational safety verification, maintenance and r
surveillance observations, and review of licensee event reports.
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Results:
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The overall performance of plant staff, during and subsequent to the
November 7,1993, reactor. recirculation pump trip was very good.
Conservatism, management oversight, and excellent teamwork on the part.
of supporting organizations, was evident (Section 2.1).
The licensee demonstrated a minor weakness in substituting manual for
automatic actions on the diesel generator fuel oil transfer pump pursuant to the guidance provided by Generic Letter 91-18 l
(Section 2.3.1).
The licensee's actions to utilize the guidance in Generic Letter 91-18
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in substituting a portable radiation monitor in place of an inoperable
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f installed radiation monitor may have exceeded the intent of the guidance. An unresolved item has been identified to track further i
review of this issue (Section 2.3.2).
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9401260128 940120 PDR ADOCK 05000458 G
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d The licensee's third utilization of the guidance provided by Generic
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Letter 91-18 was very good. Substitution of manual actions to monitor j
control rod drive unit accumulator leakage and pressure was appropriate.
Procedures were in place, personnel were trained, and proper log entries i
were made (Section 2.3.3).
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A violation was identified because of a repeat occurrence where-l
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emergency core cooling systems were rendered inoperable, at a time
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prohibited by Technical Specifications. Although adequate programmatic
controls appeared to be in place, corrective actions to prevent the
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human errors that defeated the controls did not appear to be fully l
effective (Section 2.4).
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The inspectors concluded that the licensee's training for the new l
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10 CFR Part 20 was excellent. The instructor presented the necessary l
information on how the regulations have changed and how these changes.
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affect radiation workers (Section 3.5).
c During observation of motor-operated valve motor pinion inspections, two j
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examples of procedure violations were identified. One example was
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administrative in nature, and the second example directly affected the
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results of the inspection in a nonconservative manner (Section 4.1).
j The inspectors concluded that poor planning of postmaintenance test
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instructions resulted in an inadvertent reactor water cleanup system i
isolation. A violation was identified for failure to provide adequate
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test procedures affecting safety-related equipment (Section 4.2).
j Conduct of the diesel generator surveillance was initially performed i
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effectively, but 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> later the wrong diesel generator was selected l
for the postsurveillance air roll.
Operator performance was poor in
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that the error was made, and the operators did not issue a condition report until challenged by management (Section 5.1).
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The calibration of the Division I hydrogen analyzer and monitor was
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conducted in an excellent manner, with satisfactory results (Section 5.2).
The licensee's reviews of logic system functional tests for adequacy and e
appropriateness continued to demonstrate strengths in attention to
detail.
Performance of this complex partial surveillance test was
observed to be carefully controlled and completed without incident.
(Section 5.3).
i Summary of Inspection Findings:
i Unresolved Item 458/93028-1 was opened (Section 2.3.2).
Violation 458/93028-2 was opened (Section 2.4).
e Violation 458/93028-3 was opened (Section 4.1).
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