ML20129J567
| 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: |
| 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:
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W. R. Bennett, Reactor Inspector
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:
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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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ADOCK 05000458
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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
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- W. J. Cahill, Senior Vice President
- L. Campo, Radwaste Specialist
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- T.L.Crouse, Manager-QualityAssurance(QA)
- P. J. Dautel, Licensing Staff Assistant
- J. C. Deddens, Vice President
D. R. Derbonne, Preoperations Testing Supervisor
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- R. Easlick, Radwaste Supervisor
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- L. A. England, Supervisor - Licensing
- P. E. Freehill, Superintendent Startup and Test (SU&T)
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- D. R. Gipson, Assistant Plant Manager
- K. C. Hodges System QA Supervisor
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D. Jernigan, SU&T Engineer
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- G. R. Kimmell, Supervisor Operations QA
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- G.
V.' King, Plant Services Supervisor
- M. Lett,' Radiation Protection /Radwaste
T. Pao, SU&T Engineer
- T. F. Plunkett, Plant Manager
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- 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
landed and the NRC inspector could not determine whether they were lifted
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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).
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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
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An exit interview was conducted on June 7, 1985, with those personnel
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denoted in paragraph 1 of this report.
At this exit interview the NRC
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inspectors summarized the scope and findings of this inspection.
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