IR 05000458/1985060
| ML20133L337 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/09/1985 |
| From: | Bennett W, Jaudon J, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20133L332 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.21, TASK-2.K.3.25, TASK-TM 50-458-85-60, NUDOCS 8510240112 | |
| Download: ML20133L337 (3) | |
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APPENDIX U. S. NUCLEAR REGULATORY COM4ISSION
REGION IV
NRC Inspection Report:
50-458/85-60 License: NPF-40
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. 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: September 9-13, 1985 W#
IO[9/PS Inspectors:-
W. R. Bennett, Project Engineer, Project Section A Date Reactor Projects Branch (pars. 1, 2, 4, 5)
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lok /r5 E/ Sk, Project Engineer, Project Section A
.Date-Rehet Projects Branch (pars.1 1,'3, 5)
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' Approved:
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(ReactrProjectsBranch P.(Ja on, Chief, Project'Section A
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Date Inspection Summary Inspection Conducted September 9-13, 1985 (Report 50-458/8560)
Areas Inspected: _ Routine, announced inspection of licensee identified-deficiency reports, 10 CFR 50.55(e), TMI action items and fuel load witnessing. The inspection involved 74 inspector-hours onsite by two NRC-inspectors.
Results: ;Within the three areas inspected, no violations or deviations were identified.
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- DETAILS 1.
Persons Contacted Gulf States Utilities (GSU)
- E. M. Cargill, Supervisor, Radiation Programs
- P.
J. Dautel, Licensing Staff Assistant
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- J. C. Deddens,'Vice President
- P. E._Freehill, Superintendent, Startup and Test (SU&T)
- 0. R.-Gipson, Assistant Plant Manager
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- L.- P. Handy, Quality Assurance (QA)' Engineer
- B. E. Hey, Licensing Engineer
- K.'C. Hodges,-QA Systems Supervisor
- G. ' R. Kimmell, Supervisor, Operations. QA
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- G. V. King, Plant Services Supervisor
- S. R. _ Radebaugh, Assistant Superintendent SU&T
- J. E. Spivey, QA Engineer
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- R. B. Stafford, Director - QA
- K.'G. Suhrke, Project Planning and Coordinator Manager
- P. F. Tomlinson, Director, Operations QA-
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2.
Licensee-Identified Deficiency Reports.(DRs) 10 CFR 50.55(e)
~ The purpose of this portion;of the inspection was to determine the adequacy of-corrective actions taken by.the licensee on construction deficiencies identified to the NRC pursuant to the requirements of;10 CFR 50.55(e).
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The NRC-inspectors reviewed the following " Reportable" DRs and they are considered closed:
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DR Short Title Initial GSU Final
= Number On Subject Notification Report Letter
287 Elgar UPS Fuse Block 04/04/85 RBG 20816/04/26/85'
322 Loss of Water from the 08/23/85:
RBG_22003/08/30/85 Standby Cooling Tower
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The NRC inspector determined that the deficiencies were-properly determined
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to be reportable and that all required reports were made within the appropriate time and with the appropriatefinformation.
Corrective action taken was appropriate and the deficiency no longer exists.
No violations-or deviations were identified in_this portion of the inspection.
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TMI Action Items The purpose of ~ this portion of the inspection was to determine the status of Post TMI Action Plan requirements.
NUREG 0737 Item II.K.3.21b, Restart of. Core Spray and Low-Pressure Coolant-Infection Systems.
(closed) The FSAR, Appendix 1A, page 7a, states that no modifications were made to this system and that this position was accepted in a letter from the NRC.
No implementation verification was required.
This item is closed.
NUREG 0737 Item II.K.3.25b, Effect of Loss of AC Power on Pump Seals.
(closed) The FSAR, Appendix 1A, page 8, states that testing of recirculation
. pump seals with a simulated loss of cooling water to.the recirculation pump cooling water revealed no significant leakage after 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. GSU did not feel modifications were required.
NUREG 0989, page 15-22, accepts
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this position.
No implementation verification was required.
This item is closed.
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4.
Fuel Load Witnessing The purpose of this portion of the inspection was to ascertain conformance of-licensee to license and procedural requirements and to observe operating l
staff performance.
The NRC inspectors observed the licensee load fuel.
All actions'were i
performed in accordance with the fuel loading procedure, ST-3.
Interviews with licensee personnel indicated a good knowledge of the procedure and a
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good understanding of their specific responsibilities.
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was verified to be performed in accordance with the approved procedure.
All delays in fuel loading were properly documented and fuel load properly restarted when conditions permitted.
No violations or deviations were identified in this portion of the inspection.
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' Exit Interview An exit interview was held on September 13, 1985, with the personnel
denoted in paragraph 1 of this report.
The NRC senior resident inspector also attended this meeting.
At this meeting, the scope of the inspection
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and the findings were summarized.
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