IR 05000458/1987005

Insp Rept 50-458/87-05 on 870209-13.No Violations or Deviations Noted.Major Areas Inspected:Design Changes & Mod Program,Including Program Implementation

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: IR 05000458/1987005 ML20207T283
References
50-458-87-05, 50-458-87-5, NUDOCS 8703230406
Download: ML20207T296 (4)

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APPENDIX

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U.S. NUCLEAR REGULATORY COMISSION-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 W/ 6 R. C. Stewart, Reactor Inspector, Operations Da/.e

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.Section, Reactor Safety Branch WWN . Ld./ t% 2fl9M G. A. P Lct,rinactor Engineer, Operations Date U '

SectioM, Rdactor Safety Branch Approved: b M A=Le D. M. Hunnicutt, Chief, Operations Section, A/A 5/B 7 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.

t Results: Within the two areas inspected, no violations or deviations were

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identifie D703230406 870305 PDR ADOCK 05000458 0 PDR

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DETAILS ~

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1.- Persons Contacted .

Gulf States Utilities

• R. H.. Barrow, Director

• T. F.3Plunkett, Plant Manager -

• 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, Licensi *J. H. McQuirten, Licensing NRC

• D. D. Chamberlain, Senior Resident Inspector The NRC inspectors also interviewed other licensee personne * Denotes those who attended the exit intervie .. 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 Incorporatin .b -Design' Change Documents"- ,

' *= J EDP-AA-64,: Revision51 ,'" Control!and' Approval'of Field' Change

' Notices (FCNs)"

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• s The p'rogram had provi.sionsifor: (prior'itizing the work required to b ; completed; reviewing;for Unreviewed. Safety Question Determination-(USQD);~

and conducting independent and'interdiscipline reviews to assure all

facets of the design change were considered, i.e.,' proper radiological

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controls, security. barriers, and quality control:holdpoint ,

g ;The program was satisfabtory lin'the areas examined. ' Detailed procedures 1 ' explained the control of design fchanges and processing of .these changes

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within the' Engineering a Department,'.- - , ,

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Implementation'r ,

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- _ ;The.NRC inspectorsireviewed.18-design' changes, mod'ification requests (MR), -

which included 4' prompt: modification raquests'(PMR) that:later became MR These MRs were those. determined by the River Bend Power Station to not

1. ,requ ire approval by the NRC'asi 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

' operating procedures #were changed promptly as required. Training was

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. conducted relative to the modification, if necessar The modification requests reviewed _and the system type. involved are as follows:

MR Number Sub.iect System

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-85-0059- Relay (Reverse Wiring) Electrical Power i: r E 85-0248 Spring Hanger Changes Reactor Coolant

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85-0305 Installation of Recirculation Habitability i HVAC Ductwork

[ 85-0580 Install Barrier Between Electrical

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, Cable. Trays

! 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 . I&C

(PMR86-0018) wires in MOVs 86-0929 Inspect /Realace unidentified I&C (PMRs86-0023 wiring in .imitorque actuators

& 86-0024)

86-1659 Snubber Clamp Emergency Core Cooling

1. 86-099 Modify Radwaste Control I&C Circuitry

.#86-0486 Steamline Break Detection IAC

1. 86-0738 Modify EDG Coverplates Electrical

1. Were not in permanent plant fil No violations or deviations were identifie . 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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