Text

Insp Rept 50-458/85-37 on 850506-10.No Violation or Deviation Noted.Major Areas Inspected:Correction of Deficiencies Previously Identified Per 10CFR50.55(e)
	ML20128N901
Person / Time
Site:	River Bend
Issue date:	05/29/1985
From:	Jaudon J, Will Smith; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20128N873	List: IR 05000458/1985037; ML20128N868;
References
	50-458-85-37, NUDOCS 8506030412
	Download: ML20128N901 (7)
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N.S.; NUCLEAR REGULATORY COMMISSION

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.NRC: Inspection Report: ~ 50-458/85-37 Construction Permit: -CPPR-145 '

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sDocket: 50-458

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= Licensee: Gulf States Utilities'(GS )'-

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Beaumont, Texas. :77704

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Facility Name: River Bend Station, Unit 1 (RBS)

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Inspection-At: River Bend Station, St.-Francisville, Louisiana

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1985

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-Inspection Conducted: May roug

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-Inspection Summary

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!Inspectio'n Conducted May'6 through May 10, 1985-(Report 50-458/85-37)-

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~ Areas In'spected: Routine, unannounced followup ; inspection ~of Lthe correction 'of

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y"," 'tdeficiencies-previously identified toithe NRC pursuant to 10 CFR 50.~55(e)..The l

inspection' involved.38 inspector-hours onsite by one NRC inspector.

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Results: A total.of'27 items > identified under-l'0<CFR 50.55(e)_were presented?

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toythe.NRC inspector for closure. Of these, 11-."Non-Reportable" deficiencies

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-were' closed and 16 " Reportable" deficiencies were closed.

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P i g;There were no. deviations or violations identified within;the scope of this,

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1.i: : Persons Contacted:

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J.lc.JDeddenk,Vice1 President,'RiverBendNucleasGroup-

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P. J.-Dautel, Licensing Staff. Assistant-

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vc. *T. C.;Crouse, Manager,- Quality Assurance (QA)

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_ D. R;'Gipson, Assistant Plant Manager'

R. - B.{ Stafford, Director Quality Services

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R. ET Turner,'QA Engineer

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L*I.'. M. Malik,' Supervisor, ~ Quality Engineering

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P.' D. ; Graham, ' Assistant' Plant Manager

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G.yV. - King,. ' Plant, Services * Supervisor.

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L. l Englan'd, Supervisor, Nuclear Licensing (Corporate)

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P. G.'McGill~,= Senior Electrical Engineer V. S.;Klco,- Mechanical-Engineer.

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-G. P.-' Davis, Area Coordinator

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7 W.;H.~:Benkert,. Lead Quality Engineer, Electrical Equipment Qualification

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T. F.7Plunkett, Plant Manager-

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R.. W. ; Helmick, Director,. Proj ects

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O-Sthne &' Webster Personnel

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~*B. R.lHall, Assistant Superint'endent, Field QC m..c t

R..J. Fay, Chief Electrical Inspection Supervisor,

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W.;T.- Tucker, Ass'istant-to Engineering SuperintendentJ

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?J. A.. Green, Field..QC Inspector Supervisor.

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E. L.fSigg, Construction Engineer:(General Electric (GE)'Co.)

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W. I. Clifford,~ Senior, Construction Manager'

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The NRC-inspectors also contacted other applicant employees including;

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' * Denotes those who attended the exit interview c6nducted on May;10, 19851 0-

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-The.NRC. senior;residentinspectorforconstruction,R.~ELFarrell,iaiso?

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'1Constru'c' tion Deficiency Correction Followup Inspection.

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.The purpose of this inspec. tion was to determine the adequacy of corrective

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f " attributes'were checked:thet NRC pursuant tio ;the re~quirements of 10 CFR,50.55(e). The r

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[ ( *L IThat the' deficiency was properly dbtermined to be " Reportable" or V

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"Non-Reportable" 'a's ~ defined -in 10 CFR 50.55(e)(1); '

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.If. deemed'" Reportable,'" that the' applicant submitted'a written report

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within 30'daysL(or an interim' report containing all available,

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.That; the. specific hardware (or administrative)' dificiency had been.

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(of the deficiency,,the'cause(s), an analysis of the.s'afety

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The NRC in's'pectior verified'that the correctiive act' ions had be'en completed

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'on," Reportable"ideficiencies. Most "Noa-Reportable",deficiencie's were

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thelitem.w'as not reportable'as-defined.:iny10 CFRL50,55(e)(1)s and that ~ ~

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NOTE:.DR 237 wasspreviously identified in NRC Inspection.

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Report 50-458/85-30 datsd May 10, 1985 as a.DR which could not be

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^247 eMisfabrication of pipe

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IDRI SHdRT TITLE-INITIALi GSU FINAL'

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RBG-20817/04.26-85,:

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DR-175'is considered closed-with no further questions on the

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subject of cracked batteries;ihowever, during inspection'of thei~

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-battery rack.is a-seismically: qualified structure which appears;

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Seismic ?for-20-3DCU-9 Battery.','A LThe NRC inspector. noticed that

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anot be required,at-RBS.- The;NRC-inspector 1 requested

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is: seismically. qualified:for RBS and_.is in accordance with.

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info'rmation on the hold down. brackets;(8537-01);

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'Information Notice 83-63 pertains to this).

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243 Incompatability of Bergen 09-07-84 RBG-20140/02-08-85 Patterson and Pacific Scientific pipe support parts.

249 Design deficiencies in 09-28-84 RBG-19313/10-29-84 mechanical interlocking

-

system of W. J. Wooley personnel airlocks for containment and drywell.

256 Improper scales on TDI 10-19-84 RBG-19485/11-19-84 emergency diesel generator

"A" and "B" varmeters

.and wattmeters.

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291 Inadequate design of 03-18-85-RBG-20746/04-17-85 crankshaft oil passage plugs on TDI emergency diesel generators "A" and "B".

NOTE:

The following four DRs were previously identified in NRCc Inspection ~ Report 50-458/85-30 dated May^10, 1985, as DRs

.

'

which could not be closed because'information was not provided by the end of the inspection period. Typically, the required documentation was not readily available and/or

the' final report was incomplete. During this inspection

'the required information and the revised final reports were

presented to the NRC inspector, thus allowing the items to q

be closed without further questions:

190 Incorrect. impellers 04-27-84 RBG-20927/05-07-85

installed on the low j

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pressure core spray (LPCS), high pressure j

core spray-(HPCS),

res'idual heat removal (RHR) and reactor core i

isolation cooling (RCIC)

J Pumps.

j 206 Incorrect lubricant used 06-13-84 RBG-20928/05-07-85 on fuel pool cooling pump cotors.

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lwould benefit future inspectio'ns,and : permit 'more timely ; closure' of DRs by i

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