IR 05000458/1989014

Insp Rept 50-458/89-14 on 890403-07.No Violations or Deviations Noted.Major Areas Inspected:Testing of Pipe Supports & Restraint Sys

ML20245E915
Person / Time
Site:	River Bend
Issue date:	04/20/1989
From:	Clay Johnson, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20245E913	List: IR 05000458/1989014 ML20245E910
References
50-458-89-14, NUDOCS 8905020188
Download: ML20245E915 (5)

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APPENDIX

.U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/89-14 Operating License: NPF-47 Docket: 50-458 Licensee: Gulf States Utilities (GSU)

P.O. Box 220 St. Francisville, Louisiana 70775 Facility Name: River. Bend Station (RBS)

Inspection At: St. Fr&ncisville, Louisiana Inspection Conducted: April 3-7, 1989 Inspector: GuMo b '

11 79 C. E. Johnson, R@ctor Inspector, Plant Systems Section, Division of Reactor Safety Approved: 4!2o[87 T. F. Stetka, Chief, Plant Systems Section Date Division of Reactor Safety Inspection Summary-Inspection Conducted April 3-7, 1989 (Report 50-458/89-14)

Areas Inspected: Routine, unannounced inspection of testing of pipe supports and restraint system Results: Within the areas inspected, no violations or deviations were identifie Review of the licensee's program indicated that management attention is evident in these areas. However, there were two followup items discussed in the report by the NRC inspector. Overall, the pipe supports examination and testing program is adequate.

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l 8905020188 890421 i PDR ADOCK 05000458 PDC

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DETAILS i

' Persons Contacted j

GSU

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• J. C. Deddens, Senior Vice President

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• T. C. Crouse Manager, Quality Assurance

• L. A. England, Director, Nuclear Licensing

y' *C. W. Walker, Supervisor, Quality Control (QC)

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• G. K. Henry, Director Quality Operations

• M. F. Sankovich, Manager, Engineering

• K. E. Suhrke, Manager, Project Management

[ *J.' B. Blakley, Supervisor. ASME XI

• W. H.- Odell, Manager, Administration

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• J. W. Cook, Lead Environmental Analyst, Licensing

• R..D. Carlyle, Inservice Inspection (ISI) Coordinator Cajon Electric

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• W.' L. Curran, Site Representative USNRC-

• H. Kerch, Senior Reactor Engineer, Region I

• Denotes personnel attending' exit meeting held on. April 6, 198 .~ Testing of Piping Support and Restraint Systems (70370)

The purpose of this inspection was to ascertain whether the licensee has established an adequate program and procedures pertaining to the examination and testing of piping supports and restraint system Procedure Review

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The NRC inspector reviewed the River Bend Station (RBS) ISI Plan submitted to and approved by the NRC on October 20, 1987. The NRC

. inspector also reviewed the implementing procedures for the ISI plan

'as listed below:

• ENG-3-013, " River Bend Preservice Inspection (PSI)/ISI Component Support Program," Revision 3, dated July 18, 1988

001-3.25, " Visual Examination VT-3 " Revision 3, dated July 7, 1988

• RBNP-042, "RBS American Society of Mechanical Engineers (ASME)

Section XI Program Organization, and Responsibilities.,"

Revision 1, dated July 5,1988

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• - EDP-ME-63, " PSI /ISI Forms Management," Revision 4, dated

' June 15, 1988

EDP-ME-58, " PSI /ISI Component Support Examination and Testing Package Preparation, Control and Storage," Revision 3, dated May 3, 1988

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ENG-3-012 ,"ASME Section XI PSI /ISI Documentation Control,"

p Revision 1, dated June 21, 1988

0C1-3.26. " Visual Examination VT-4," Revision 3, dated July 7, i 1988

Technical Specification (TS) 3/4.7.4, " Snubbers"

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Procedures reviewed by the NRC inspector appear to be adequat It was also noted that the licensee has submitted Technical Specification Change Request (TSCR) 87-0028 to delete snubbers from the TS and use only the ISI plan. Review of the ISI plan and the amendment' change indicates that very little will change. It appears _that the ISI plan will be more specific in the types of snubbers to be included in the ISI program. This change is consistent with.the NRC plan to place all snubber surveillance activities under the ISI pla . Field Observations of Pipe Supports The. NRC inspector examined approximately 25 pipe supports of various types and systems. Attributes that were selected for observation in the visual examination are listed as follows:

Deterioration, corrosion, physicoi damage, or deformations were not evident,.  :

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All required bolts, locking devices, nuts, and washers were !

f-L- installed;

• Extension rods, support plates, and connecting joints were not bent, deformed, or loose; h

• Snubber settings; Pipes, supports, or other associated equipment or components were not restricted or in contact with other surfaces as a l result of thermal expansion;

• Springs in hangers were not obstructed by foreign material;

• Indicators or spring hangers show either " cold" or " hot" position, consistent with plant condition; and

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Threaded connections were secured by locknuts, fasteners, and cotter pin Supports examined are listed below:

Support No !

1RHS * PSSH-2167-A2 1RHS'* PSST-2347-A2 i~

IWCS * PSSP-3023-Al 1SLC * PSSP-3122-A2 ISWP *' PSST-1441-A3 ISWP * PSSP-1610-A3 25WP * PSST-1761-A3 ISWP * PSR-1432-A3 j ISVV * PSSP-3021-A3

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1SWP * PSST-1374-A3 ISVV * PSSP-3053-A3 ISVV * PSSP-3119-A3 ISVV * PSSH-3120-A3 ISVV * PSSP-3124-A3 j ISVV * PSSH-3132-A3

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ISVV * PSSP-3134-A3 l 1SVV * PSSP-3135-A3 ISVV * PSSP-3203-A3 ISVV * PSSP-3227-A3 1CSL * PSSP-2010-A3 1CSL * PSSP-2012-A2 1CSL * PSSH-2002-A2 ISWP * PSSP-1447-A3 ISWP * PSSP-1433-A3 1CSL * PSST-2008-A2 Overall, the pipe supports examined appeared acceptable, however, there were two discrepancies noted below:

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(1). Inspection of the service water system (SWS) on Train "B" indicated that many supports contained from light to heavy rust ..

deposits on various parts of the support. Some welds had not  !

been painted and showed excessive oxidation and rust deposits on the welds. This finding was discussed with licensee-representative The licensee had selected Train "A" for their ISI sampling pla This plan is consistent with IWF-2510 (b) of Section XI which states, that, ". . . multiple components within a system of similar design, function, and service, the supports of only one i of the multiple components are required to be examined." Based i upon the inspector's findings, it appears that increased j surveillance activities by QC should be performed on Train "B"  !

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supports in the area because of the observed corrosion problems

.n the SW The Director of Field Engineering has submitted a memorandum dated. April 6,.1989, to QC requesting additional surveillance on supports' located near sample supports to identify whether unsatisfactory conditions exist. This item is considered to be an NRC inspector followup ite Inspector Followup Ite.n (458/8914-01): Review proposed increased l QC surveillance for adjacent pipe supports not included on the j ISI sampling pla l l

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(2) 'During the inspection inside containment, the NRC inspector noted that Spring Hanger ISVV * PSSH-3120-A3 located inside the drywell, had bottomed out according to the indication scal Review of the previous inspection conducted by QC indicated that'

during Refueling (RF) Outage 1, the support setting was acceptabl The licensee is presently investigating this finding. This item

. is considered to be an NRC inspector followup ite <

Inspector Followup Item (458/8914-02): Review licensee's investigation of Hanger ISVV * PSSH-3120-A3 located inside the drywell, Inservice Tests for Snubbers The. NRC inspector witnessed functional testing performed on Snubbers ISVV * PSSP-3018-A3, 1WCS * PSSP-2019-A3, 1TCS * PSSP-2107-A2, and ISVV * PSSP-3014-A3. Observations by the NRC inspector indicated the '

following:

Personnel performing the testing were qualifie *

Proper instructions and procedures were followe *

The functional test machine and accessories were calibrated as require *

As-found drag force, activation / acceleration, and as-left-drag force were within acceptable limit The licensee's testing program is being conducted by a contractor (Wyle Laboratories). It appears that the' licensee's testing program is adequat In conclusion, the licensee has established an adequate program and implementing procedures' for the examination and testing of pipe support . Exit Interview The NRC inspector met with the licensee personnel (denoted in paragraph 1)

on April 6,1989, and summarized the scope and findings of this inspection. No information was identified as proprietary.

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