IR 05000458/1987005
| ML20207T296 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 02/25/1987 |
| From: | Hunnicutt D, Greg Pick, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20207T284 | List: |
| References | |
| 50-458-87-05, 50-458-87-5, NUDOCS 8703230406 | |
| Download: ML20207T296 (4) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMISSION
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-REGION IV
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NRC Inspection Report:
50-458/87-05'
License:
NPF-47 Docket:
50-458
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Licensee: Gulf States Utilities P. O. Box 220 St. Francisville, Lo'uisiana
.70775 Facility Name:
River Bend Power Station Inspection At:
St. Francisville, Louisiana
Inspection Conducted:
February 9-13, 198 /
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Inspectors:
s R. C. Stewart, Reactor Inspector, Operations Da/.e
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.Section, Reactor Safety Branch WWN Ld./
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G. A. P Lct,rinactor Engineer, Operations Date U
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SectioM, Rdactor Safety Branch Approved:
b M A=Le A/A 5/B 7 D. M. Hunnicutt, Chief, Operations Section, Date
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Reactor Safety Branch Inspection Summary
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Inspection Conducted February 9-13, 1987 (Report 50-458/87-05)
Areas Inspected:
Routine, unannounced inspection of design changes and modification program including program implementation.
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Results: Within the two areas inspected, no violations or deviations were t
identified.
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D703230406 870305 PDR ADOCK 05000458
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f DETAILS
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Persons Contacted
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Gulf States Utilities
- R. H.. Barrow, Director
- T. F.3Plunkett, Plant Manager
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- M. F. Sankovich, Manager,~ Engineering
- W..H. Odell, Manager, Administration
- D.-R. Gibson, Director Quality Services
- J. R. Hamilton, Director, Design Engineering
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- E. R. Grant, Director, Nuclear Licensing
- D. J. Krueger, Supervisor, Engineering -Administration
- V. J. Normand, Supervisor, Administrative Services
- K. C. Hodgen Supervisor, Quality Assurance, Engineering
- R. J. King, Supervisor, Nuclear Licensing
- L. A. England, Supervisor, Licensir.g 1*J. H. McQuirten, Licensing NRC
- D. D. Chamberlain, Senior Resident Inspector The NRC inspectors also interviewed other licensee personnel.
- Denotes those who attended the exit interview.
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Design Changes and Modifications Program The NRC inspectors reviewed the licensee's program for design changes and modifications as delineated in the following procedures:
ADM-D019, Revision 5. " Initiation and Processing of Condition
Reports" ADM-0028,' Revision 7. " Maintenance Work Order"
RBNP-010, Revision 3 " Design and Modification Control"
ENG-3-006, Revision 2, " River Bend Station Design and Modification
Request Control Plan" EDP-AA-21, Revision 0,"PipingandInstrumentationDiagram(P&ID)
Redline and Review Process" EDP-AA-54. Revision 8. " Engineering Department Guidelines and
Instructions for Processing Modification Requests"
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2EOP-AA-59,-Revision'6,2" Tracking, Distributing, and Incorporating.
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.b -Design' Change Documents"-
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EDP-AA-64,: Revision 1,'" Control!and' Approval'of Field' Change
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' Notices (FCNs)"
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The p'rogram had provi.sionsifor: (prior'itizing the work required to be..
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and conducting independent and'interdiscipline reviews to assure all
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facets of the design change were considered, i.e.,' proper radiological
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controls, security. barriers, and quality control:holdpoints.
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- The program was satisfabtory lin'the areas examined. ' Detailed procedures g
' explained the control of design fchanges and processing of.these changes within the' Engineering Department,'.-
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Implementation'r J.
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- The.NRC inspectorsireviewed.18-design' changes, mod'ification requests (MR),
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which included 4' prompt: modification raquests'(PMR) that:later became MRs.
These MRs were those. determined by the River Bend Power Station to not i
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,requ re approval by the NRC'as a resultiof review pursuant to
'10 CFR Part 50.59. The MRs were reviewed and approved in accordance with
1 Technical' Specifications (TS) and established quality assurance / quality control: guidelines.'.. Testing, if applicable, was'within previously established acceptance criteria. Control room.as-built drawings and
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' operating procedures #were changed promptly as required. Training was
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. conducted relative to the modification, if necessary.
The modification requests reviewed _and the system type. involved are as follows:
MR Number Sub.iect System-85-0059-Relay (Reverse Wiring)
Electrical Power
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85-0248 Spring Hanger Changes Reactor Coolant
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85-0305 Installation of Recirculation Habitability i
HVAC Ductwork
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85-0580 Install Barrier Between Electrical Cable. Trays
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85-0761 <
Reset setpoints for Containment Containment Airlocks Reset i
to Meet TS
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85-0950 Switch Contact Conductor Instrument and Control Change (I&C)
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85-0956 Keylock Switch'Added to I&C Lockout RHR Suction 85-1236
' Modify Pressure Tight Door Control Building Elevator 85-5119 ASCO Solenoid (Torque)
I&C Valves Incorporated into Installation Manuals 86-0491 Substitute Power Supply Plant Power 86-0535 Added Timing Relay to I&C Annunciator Control Circuit 86-0724 Replacement of Nonidentifiable.I&C (PMR86-0015)
wires in MOVs with qualified wire 86-0776 Replace of unidentified
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wires in MOVs 86-0929 Inspect /Realace unidentified I&C (PMRs86-0023 wiring in.imitorque actuators
& 86-0024)
86-1659 Snubber Clamps.
Emergency Core Cooling
- 86-099 Modify Radwaste Control I&C Circuitry
.#86-0486 Steamline Break Detection IAC
- 86-0738 Modify EDG Coverplates Electrical
- Were not in permanent plant file.
No violations or deviations were identified.
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Exit Interview The NRC inspectors met with the personnel denoted in paragraph 1 on February 13, 1987, and summarized the scope and findings of the inspection. The licensee acknowledged the inspector's consents.
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