IR 05000498/1988045

Insp Repts 50-498/88-45 & 50-499/88-45 on 880711-29.No Violations or Deviations Noted.Major Areas Inspected: Verification of as-builts (Structures)

ML20151V356
Person / Time
Site:	South Texas
Issue date:	08/12/1988
From:	Barnes I, Ellershaw L, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151V343	List: IR 05000498/1988045 ML20151V340
References
50-498-88-45, 50-499-88-45, NUDOCS 8808220242
Download: ML20151V356 (6)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report; 50-498/88-4L Operating License: NPF-76 50-499/88-45 Construction Permit: CPPR-129 Doi:kats: 50-498 50-499 Licensee: Houston Lighting & Power Company (HL&P)

P.O. Box 1700 Houston, Texas 77001

, Facility Name: South Texas Projed (STP), Units.1 and 2 Inspection At: STP, Matagorda County, Texas Inspection Conducted: July 11-29, 1988 Inspectors: 2 /!p!(f'

L: E. 'El le@ haw, Reactor Inspector, Materials DcKf

' p nd Quality Programs Section, Division of Reactor Safety Yrm $bt fl'

W. M. McN6ill, Reactor Inspector, Materials .

and Qudlity Programs-Section, Division of -

Reactor Safety-Approved: wes .

. Barnes, Chief, Materials and Quality

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k/kf Date Prograns Section, Division of Rdactor Safety Inspection Summary Inspection Conducted July 11-29, 1988 (Report 50-498/88-45)

Areas Inspected: No inspection =of Unit I was conducte Results: Not applicabl %s2gy h {

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2-Inspection Conducted July 11-29, 1988 (Report 50-499/88-45)

Areas Inspected: Routine, unannounced inspection of the verification of as-builts(structures).

Resul' * WitSin the area inspected, no violations or deviations were ident ed

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l-3-u i AIM Persons Contacted HL&P

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• J. Bailey, Manager, Engineering and Licensing D. Dujka, Civil Engineer

• H. L. Duke, Staff Engineer

• J. E. Geiger, General Manager Nuclear Assurance

• A. W. Harrison, Supervising Project Engineer

• S. M. Head, Supervising Project Engineer

• T. J. Jordan, Project Quality Assurance (QA) Manager, b;.' , 2

• A. R. Mikus, General Superintendent Construction

• D. Parker, Startup Engineer

• G. L. Parkey, Plant Superintendent, Unit 2

• M. F. Poloshak, Project Compliance Lead Engineer

• D M. O'Gara, Project Compliance Engineer

• S. L. Rosen, General Manager, Operations Support

• J. A. Siabinski, Unit 2 Operations Quality Control (QC) Supervisor

• J. T. We:termeier, South Texas Project (STP) General Manager

• M. Wisenburg, Plant Superintendent, Unit 1 Bechtel Engineering Corporation (SEC)

• L. W. Hurst, Assistant Project Manager A. Lopez, Structural Supervisor

• K. P. McNeal, Project QA Engineer

• C. F. O'Neil, Unit 2 Engineering Manager R. Schulman, Lead Civil Engineer Ebasco Service In D. Higby, QA Piping Supervisor R. Irish, QA Inspector

• R. A. Moore, Assistant QC Site Superintendent

• P. E.-Phelan, QA Structural and HVAC Supervisor

• E. P. Rosoc, Site Manager

• R. C. Sisson, Site Resident Engineer J. Stevens, QA Supervisor R. Wagner, QA Inspector

• Denotes personnel attending exit meetin The NRC inspectors also contacted other personnel including administrative and clerical personnel during the course of the inspectio .. .

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-4- Verification of As-Builts Structures (37051)

The objectives of this inspection were to determine whether the as-built design and construction drawings and specifications correctly reflect the as-built structural condition of the plant; changes from the original design were properly reviewed and approved; and that plant seismic and other stress calculations were based on as-built condition In this regard, the NRC inspectors reviewed the quality assurance program description, Revision 21, dated February 18, 1988, found in the Safety Analysis Report, and the following implementing procedures, specifications, and instructions:

Fabrication, Erecticn and Bolt-Up of Structural and Miscellaneous Steel, SSP-11, Revision 3, dated March 8, 1988, with Interim Change Notices (ICNs) through 1 General Structural Welding Requirements, SSP-16, Revision 3, dated July 15, 1986, with ICNs through 2?..

Engineering Review Walkdowns, SSP-61, Revision 2, dated December 28, 198 Unit 2 Structural Steel Mapping Instructions, dated April 22, 198 *

Specification for Category I Structural Steel, 3A010SS0012, Revision 5, dated August 22, 198 Specification for Erection of Stri ctural and Miscellaneous Steel, 3A010SS0026, Revision 8, dated June 15, 1987, with Field Change Notices (FCRs) BC 3741, BC 3848, and DC 253 The NRC inspectors performed a walkdown covering each elevation of all seismic Category I buildings, during which the structural steel connections were visually examined. During the walkdown, the NRC inspectors noted that a diagonal brace, which was shown on the design drawing, had been deleted from a platform at elevation -21 feet in the fuel handling building. The licensee did, however, provide a FCR No. EC-02216 which documented this change and the design review of the change. In-the performance of the walkdown, a sample of 18 connections was established and each connection was inspected in detail. The sample is described below:

Building * Elevation Drawing / Mark No. Configuration **

(Feet) Connection DGB 35 5002/26C 36AZ BM to embed RCB -2 1502/33 127B3 BM to BM 156B2 i

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-5-RCB -2 1502/32 182C10 Col to BM 127B3 RCB -2 1619/10 15081 BM to BM

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15082 RCB 37 1621/23 30182 BM to embed RCB 52 1622/58 404B1 BM to BM (1506/62) 404B2 RCB 37 1621/16 31186 BM to embed (1506/86)

FHB 53 3008/120 302B4 BM to BM 305B6 to BM 308B8

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FHB 42 3008/269 304C2 Col to BM 305B4- to BM to BM 308B9 308811 MEAB 60 4042/100 706B4 BM to embe MEAB 70 34003/122 2387 BM to embed MEAB 70 4020/63 H8166 Col to BM i C8164 to BM C8165

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MEAB 4020/64 A8165 BM to BM

.C8164 to BM M8163 MEAB 67 4020/56 42AZ' BM to embed 4020/62 42B2 BM to embed 4020/73 K8163 BM to embed

'MEAB '80 4032/2 72A1 BM to embed MEAB 69 4043/146 71184 BM to embed

• Building Abbreviations DGB-diesel generator building RCB-reactor containment building FHB-fuel handling building HEAB-mechanical electrical auxiliary' building

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• • Structural Component Abbreviations BM-beam embed-embedded plate Col-column

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The sample selected for inspection consisted of welded, bolted, and a combination of connections. The design drawings for each of the connections were reviewed in order.to establish beam and column size and configuration, weld size and location, bolt size and quantity. The NRC inspectors-physically verified, by direct measurement, all of the accessible attribute The NRC inspectors reviewed the licensee's. inspection documentation, mapping drawings, report data sheets, vendor cut sheets, mark drawings, and inspection reports for torque testing for bolting and AWS D '

structural welding. All applicable deficiency. notices, nonconformance reports, requests for engineering assistance were also reviewed. It was-also noted that four of the connections (those identified with a 1600 series drawing) had been part of a redesign effort associated with thermal expansion joints. The redesign documentation and five additional FCRs were reviewe No violations or deviations were identifie . Exit Meeting -

The NRC inspectors conducted an exit meeting on July 29, 1988, with the licensee personnel denoted.in paragraph 1. The NRC resident inspector also attended. At this meeting, the scope and findings of.the inspection were summarize .

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