IR 05000415/2006027

Insp Rept 50-458/85-33 on 850415-0627.Violation Noted: Failure to Adequately Document Changes to Insp Rept Results

ML20137E936
Person / Time
Site:	River Bend, 05000415
Issue date:	08/15/1985
From:	Gilbert L, Jaudon J, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20137E926	List: IR 05000415/2006027 ML20137E923
References
50-458-85-33, NUDOCS 8508260105
Download: ML20137E936 (7)

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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspe$ tion ~ Report: -50-458/85-33~ Construction Permit: CPPR-145 Docket: 50-458 Licensee: Gulf States Utilities (GSU)

.. O. Box 2951 Beaumont,. Texa Facility Name: Rive'r Bend, Unit 1 l Inspection t: River Bend Site Inspection Conducted: Ap'ril 15-June 27, 1985

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Inspectorst:- + , SM Date

/ S~ T L.D. Gilbert,ReactorInspector[]

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As Ye Y W. M. McNeill, Reactor Inspector Date I

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Approved: M# /.$ '

J./P. laudpfi; Chief, Preject Section A, Reactor

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Date (Pjoj hCt Branch -

Inspection Summary ,

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Inspection Conducted April 15-June 27, 1985 (Report 50-458/85-33)-

Areas Inspected: Routine, unannounced inspection of safety-related pipe supports and verification of as-builts-for piping system The inspection ..

involved 198 inspector-hours onsite and 3 inspector-hours offsite by two NRC-inspector Results: -Within the two ' areas inspected, one violation was identified (failure

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to adequately document changes to inspection report results, paragraph 3.b). ,

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-2-DETAILS _ Persons Contacted

, Principal Licensee Personnel

• B. Stafford, Director Quality Services

• M., E. Walton, Supervisor Design Engineering

• R. E. Turner, Quality Assurance Engineer

• P. J. Dautel, Licensing Staff Assistant

• T. C. Crouse, Manager Quality Assurance

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• T. F. Plunkett, Plant Manager

• L. A. England, Supervisor - Licensing

• I. M. Malik, Supervisor Quality Engineering

• D. R. Gipson, Asst. Plant Manager - Operations Stone & Webster (S&W) Personnel

• R. L. Spense, Resident FQC Manager

• I. Clifford, Senior Construction Manager

• T. Tucker, Assistant to Superintendent of Engineering

• B. R. Hall, Assistant Superintendent FQC

• R. J. Fay, Chief Inspection Supervisor FQC R. Whitley, Assistant Superintendent FQC

.J. Green, FQC E. Fisher, FQC R. Ferguson, QC Engineer D. Cowart, FQC W. Wagner, FQC W. Edasi, Site Reconciliation Group Engineer

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J. Brock, FQC S. Fitzpatrick, FQC E. Tomlinson, FQC

• Denotes those attending the exit interview on June 14 and/or June 27, 198 . Safety-Related Pipe Supports Dynamic Pipe Supports The objectives of this inspection were to determine by visual examination that components were free from corrosion, not bent, deformed or loose, properly lubricated, free from foreign material that would obstruct operation and that fasteners were to be secure and of the correct material A sample of seven Pacific Scientific Compcny snubbers were inspected by the NRC inspector. Approximately 300 of this type of component

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-3-are installed at River Bend. The visual inspection found the snubbers to have dirt, dust, and paint yet to be removed. S&W had not, as of the time of this inspection, performed a final cleanliness inspectio The final clearance inspection (CSI-8.1.1) had yet to be performed as a result the clearance of the pipe clamp, and snubber paddle on

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one snubber (1-BZ-108AAr) had yet to be evaluated. The Nspection noted that one snubber (support 1-BZ-11 HP) was stiff to rctat The cleanliness and clearance inspection was performed subseauently (see 3.b following). The supports inspected are listed belo Hanger N Support N Model N Bld./Elv 1 DTM*PSSP 3004A1 1-BZ-31PW PSA 1 RB/125 1 MSS *PSSP 3033Al 1-BZ-2DD PSA.25 RB/155 1 RHS*PSSP 2367A2 1-BZ-71XD PSA 10 AB/73 1 FWS*PSSP 3031A1 1-BZ-17dS PSA 35 RB/137

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1 RCS*PSSP 3040A1 1-BZ-970AU PSA 35 RB/108 1 SWP*PSSP 1371A3 1-BZ-108AAF PSA 35 GT/78 1 SVV*PSSP 3203A3 1-BZ-11 HP PSA 35 RB/107 Component Supports ' The objectives of this inspection were to determine by examination that location, welding certification of materials, and design clearances comply with design drawings, specifications, and code requi rement A sample of six component st pports were inspected (see table below).

The first three listed in the table are multiple type pipe support The location of the supports and other drawing dimensions were-verified by the NRC inspector by actual measurements. The welding of the components and their installation was inspected. This examination included verification of the welder qualifications, weld dimensions and the weld surface condition. The applicable design specifications and drawings were reviewed in order to establish the requirements. The certified material test reports (CMTRs) of the supports were reviewed to verify their conformance with specification and code requirements. In this regard Code Case N-225 was noted to have been invoked, however, CMTRs were found to be on file for the materials sample One minor dimensional discrepancy was observed by the NRC inspector on support 1-RHS-196* PSP-3A; however, an N&D 11712 was issued and the "as built" drawing revised. The welding on the standby service water pump motor stand was noted by the NRC inspector to be

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-4-particularly questionable. This was documented on N&D 11990 and

'also addressed in E&DCR C-7271. Nuclear Construction Issues Group (NCIG) requirements were invoked, and these welds were found to be acceptable. One problem was identified on the materials of support 1-BZ-1088G. The material call out~ change was documented on N&D 11658 and accepted. This problem was the result of a drawing change which had not been made retroactiv Support / Hanger N Drawing N Location

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1-RHS-196* PSP-3A 1-BZ-RHS-196*003 AB/77 1-BZ-1088G 1-BZ-1088G DT/78 1-HVN*PSR 2026AZ 1-BZ-770CB -AB/147 1-SFC*SUP-1AB 1-SFC*SUP-1AB FB/82 Non-Regen. H. RB/146 (Teledyne Brown)

SSW pump motor stand 1-500-153 Standby Service (Haywood Tyler) Water Tower Pipe Anchor Locations The objectives of this inspection were to examine anchors and compare them with the drawings to ensure agreement as to their location and functio A sample of 4 of the 200 plus anchor locations were inspected by the NRC inspector-(see table below). The drawings were reviewed to establish dimensional requirements. The dimensions were verified by field measurements. The apparent function was verified at the same tim Anchor N Drawing N Location 1-ICS*PSA 2014AZ 1-BZ-76L AB/86 1-SFC*PSA 4061A3 1-BZ-77BN FB/90 1-SWP*PSA 3034A3 1-BZ-19ANW RB/159 1-WCS*PSA 2016A3 1-BZ-74AE AB/107 As-Built Configuration The NRC inspector selected three as-built safety-related pipe support structural drawings and compared the following selected supports with the actual installatio . _ __ _ _ ___

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(1)- Reactor Water Clean-up System - Class 1 Piping Line 1-WCS-003-006-1;

• Hanger 1 WCS*PSSP3039Al

• Hanger 1 WCS*PSSH3041A1

• Hanger 1 WCS*PSSP3042A1

• Hanger 1 WCS*PSSP3207Al

• Hanger 1 WCS*PSSH3045A1

• Hanger 1 WCS*PSSP3044A1

• Hange WCS*PSSP3005A1

.: (2) Low Pressure Core Spray System - Class 1 Piping Line 1-CSL-010-42-2;

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Hanger 1 CSL* PSST 2033A2

• ~ Hanger 1 CSL*PSSP2034A2

• Hanger 1 CSL* PSST 2035A2

• Hanger 1 CSL*PSA2055A2

• Hanger 1 CSL*PSSH2054A2

* Hanger 1 CSL*PSSP2056A2 (3) Feedwater System - Class 2 Piping Line 1-FWS-020-062-2;

! * Hanger 1 FWS*PSR2011A2

• Hanger 1 FWS*PSSP2010A2

• Hange FWS*PSSP2008A2

• Hanger 1 FWS*PSSP2007A2 .

• Hanger -1 FWS*PSSP2006A2

• Hanger 1 FWS*PSSP2005A2

• Hanger .1 FWS*PSSH2004A2 In the areas inspected, the installed supports.were consistent with the as-built drawings and dimensional tolerances specified iri S&W Specification 228.312 except for cne minor dimensional discrepancy for Hanger 1-WCS*PSSP3207Al which was determined to be a measurement

, error and dispositioned use-as-i The as-built drawing was revised to show the correct dimension. This measurement error appears to be an isolated cas No violations or deviations were identifie . Verification of As-Builts Safety-Related Piping Systems The NRC inspector selected eight piping isometric drawings for comparison of the drawing to the as-built condition. The eight i drawings listed below represent four safety-related piping systems

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and 180 feet of piping ranging in sizes from 10 to 20 inches in

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-6-(1) Residual Heating' Removal System - Class 1

• Drawing 1-RHS-034-CD-B

• Drawing 1-RHS-034-CD-A

• Drawing 1-RHS-067-CD-A (2) Feedwater System - Class 1

• Drawing 1-FWS-047-CD.-A (3) Low Pressure Core Spray - Class 2

• Drawing 1-CSL-42-CD-A (4) High Pressure Core Spray - Class 2

• Drawing 1-CSH-014-CD-B

• Drawing 1-CSH-004-CD-A

• Drawing 1-CHS-004-CD-B In the areas inspected. the installed piping, including welds and supports, were consist ant with the as-built drawing and dimensional tolerances specified in S&W specification 228.312 except for a support that had been added by Rework Control Form ABP-1336 and a minor dimensional discrepancy for the location of Hanger 1-BZ-83 A The new support added by ABP-1336 was in the process of being incorporated into the as-built drawing. :The minor dimensional discrepancy for Hanger 1-BZ-83AY was determined to be a draf ting error which was promptly corrected. The drafting error appeared to be an isolated case, Clearances Around Safety-Related Pipino Systems The NRC inspector selected two piping systems to inspect for compliance with S&W Construction Site Instruction (CSI) 8. for adequate clearances around the piping and supports. The two piping systems inspected were the low pressure core spray

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(CSL) system and the residual heat removal (RHS) system. The portion of the CSL system inspected was designated as Class 2

and identified on Drawing 1-CSL-42-CD-A. The portion of the RHS system inspected was designated as Class 1 and identified on Drawings 1-RHS-034-CD-A and 1-RHS-034-CD- In the areas inspected the clearances around the pipe, components and supports were consistent with the movements indicated by the reconciled AX load sheet for those areas

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evaluated by the Site Reconciliation Group (SRG) engineers during the-area walkdown and cansistent with CSI 8.1.1. The NRC inspector selectively inspected work performed after the SRG area walkdown for compliance with general clearance

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requirements of CSI 8.1.1. The work inspected for general ,

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clearances included the following items of work from various s'

craft discipline * Work Control Form CCC No. 5-06-11-RB-4792 for Floor Grating in Reactor Building

• Work Control forms CCC No. 5'-05-11-AB-33508 and CCC No. 5-05-11-AB-33510 for Lighting Transformers in Auxiliary Building

• Cable Pull Tickets 1HTSNNC013'and 1HTSNNX012 for Electrical Cable in Auxiliary Building

• Rework Control Form.Nos. ABP-1656 and ABP-1669 for Pipe Supports in Control Building In the areas inspected, the general clearances were consistent with'CSI 8. However,.while reviewing the inspection report for two of the pipe

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supports, the NRC inspector determined that the results for the general clearances attribute on Inspection Report No P5400381 dated June 12, 1985, had been changed on June 13, 1985, from "not applicable" to " satisfactory" by a reviewer who neither had performed the inspection nor had any other inspection documentation to support the chang ihe two pipe supports identified in Inspection Report No. F5400381 were inspected by the NRC inspector and were found to be in compliance with the general clearance requirements of CSI 8.1.1 Revision 4.

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A preliminary review by the licensee determined that a small percentage of other safety-related inspection reports contained

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i This is an apparent violation of Crite.rion XVII of 10 CFR 50, i Appendix B, in that sufficient records were not maintained to

! furnish evidence that the inspector of record performed the

inspectio (458/8533-01).

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4. Exit Meeting The NRC inspectors met with licensee representatives (denoted in paragraph 1) and the NRC senior resident inspector, on June 14 and i June 27, 1985, and summarized the scope and findings of the inspection.

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