IR 05000458/1983010
| ML20023D862 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/13/1983 |
| From: | Brown R, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20023D858 | List: |
| References | |
| 50-458-83-10, NUDOCS 8306060073 | |
| Download: ML20023D862 (6) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/83-10 Docket: 50-458 Permit: CPPR-145 Licensee: Gulf States Utilities (GSU)
P. O. Box 2951 Beaumont, TX 77704 Facility Name: River Bend, Unit 1 Inspection At: River Bend Inspection Conducted: April 7,1983, through April 30, 1983.
/E'A Inspector:
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l Ross L. Brown, Senior Resident Inspector Date Approved:
5//3/9.3 W. A. Crossman, Chief Date Reactor Project Section B Inspection Summary Inspection Conducted April 7-30,1983 (Report: 50-458/83-10)
l Areas Inspected:
Routine, announced inspection of site tour; licensee identified construction deficiencies; safety-related pipe welding; safety-related pipe supports and restraints; and electrical system installation. The inspection I
involved 74 inspector-hours onsite by or,e NRC inspector.
l Results: Within the five areas inspected, no violations or deviations were l
identified.
l 8306060073 830517 PDR ADOCK 05000458 G
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DETAILS 1.
Persons Contacted Principal Licensee Employees
- P. D. Graham, Director, Quality Assurance R. B. Stafford, Supervisor, Quality Assurance
- M. E. Walton, Supervisor, Site Engineering (Beaumont)
W. J. Reed, Director, Nuclear Licensing (Beaumont)
L. A. England, Lead Licensing Engineer R. J. King, Licensing Engineer (Beaumont)
- T. C. Crouse, Project Engineer G. R. Kimmell, 0A Engineer D. G. Seymour, QA Engineer C. L. Ballard, Supervisor, Quality Systems P. J. Dautel, Licensing Staff Assistant (Beaumont)
R. E. Turner, QA Systems Stone and Webster (S&W)
- R. L. Spence, Superintendent, Field Quality Control (FQC)
B. R. Hall, FQC Senior Engineer N. W. Pressler, FQC Chief Inspector, Electrical R. J. Fay, FQC Supervisor, Electrical D. Whitlock, FQC Inspector Supervisor D. P. Barry, Superintendent, Engineering G. M. Byrnes, FQC Assistant Superintendent V. L. Barton, FQC Inspection Supervisor W. I. Clifford, Senior Construction Manager
- J. J. Zullo, QA Program Administrator R. L. Whitley, FQC Assistant Superintendent
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l D. M. Cowart, FQC Senior Inspector
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F. Finger, PT0/ Project Manager The Senior Resident Inspector (SRI) also interviewed additional licensee, S&W, and other contractor personnel during this inspection period.
- Denotes those persons that attended the management interview.
2.
Site Tour The SRI toured creas of the site during the inspection period to observe construction progress, general job practices, housekeeping, and fire protection.
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3.
Follow Up On Licensee Identified Deficiency Reports,10 CFR 50.55(e)
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(Closed) Deficiency Report (DR-77/GSU letter RBG-13736) " Violation of Minimum Spacing Between Drilled-In Anchors and Embedments." The'
SRI reviewed the S&W letter RBS-8210 to GSU and four referenced documents; Report of a Problem (R0AP) RBI-C-018, N&D 2856, 2941, and 2955 that identified the deficiency; giving each anchor location and the engineering justification for the accept-as-is disposition.
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The SRI also reviewed S&W Specification 210,371, Attachments 1, 2, i
and 3 that have been revised to more clearly delineate the program
requirements including inspection.
The-SRI reviewed the GSU Memorandum RBG-14,102 that states GSU project engineer and director of QA concur with the S&W evaluation that the deficiency is not reportable under 10 CFR 50.55(e) requirements.
The SRI concurs that the condition is not reportable.
Item is closed.
(Closed) Deficiency Report (DR-69/GSU letter RBG-13,236) " Intermixing
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of E308-16 Welding Electrodes with E309-16 Welding Electrodes Supplied
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by Chemetron Corp." The SRI reviewed N&D 2706 that describes the problem
with the 3/32-inch electrodes and the engineering justification and disposition.
The SRI also reviewed S&W letter RBS-8207 to GSU that described the S&W
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evaluation and justification in detail.
The SRI reviewed GSU letter RBG-14,196 to S&W stating that their review of S&W letter RBS-8207 indicates certain deficiencies.
S&W letter RBS-8429 to GSU provide the supplemental information requested in GSU letter RBG-14,196.
GSU Memorandum RBG-14,683 states that GSU's project engineer and director
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of QA concur that the deficiency should be closed.
The SRI concurs that the condition is not reportable under 10 CFR 50.55(e).
Item is closed.
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(Closed) Deficiency Report (DR-94/GSU letter RBG-14275) " Vendor Substituted a 90 Degree Welded Elbow for a Seamless Elbow."
The site received one 10-inch short radius 90 elbow, SA403-WP304 WX,
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(welded) from their supplier (Gulfalloy, Inc.) who purchased the item from G&W Taylor Forge Stainless, the manufacturer of the elbow.
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-4-The SRI reviewed the S&W Report of a Problem RBI-FQC-008 that states the material manufacturer (G&W Taylor Forge Stainless) holds an ASME Quality System Certificate (Material) 269 that accredits them as being a manufacturer of ferrous seamless tubular products not welded.
The SRI reviewed an ASME letter dated June 19, 1980, to G&W Taylor Forge Stainless in reply to G&W Taylor Forge Stainless letter of May 29, 1980:.
that tubular products welded without filler metal should have been included in both Quality System Certificates QSC-269 and QSC-270.
The SRI reviewed the Quality System Certificate (Materials) QSC-269 dated March 3, 1980, revised June 23, 1980, that accredits G&W Taylor Forge Stainless as a material manufacturer of ferrous seamless and welded without filler metal tubular products.
The SRI concurs the condition was not reportable under 10 CFR 50.55(e).
Item is closed.
4.
Safety-Related Pipe Welding The SRI reviewed the S&W Specification 228,160, " Field Fabrication and Erection of Piping," for ASME III, Code Classes 1, 2 and 3 and ANSI B 31.1 Class 4, which specifies the weld control requirements related to:
the alignment, weld material control, applicable codes and standards, weld data sheets, weld profile and finish, and cleaning and nondestructive examination.
The SRI observed the installation and welding of joints in the feedwater, service water, residual heat removal, and reactor core isolation cooling piping systems and reviewed the document packages at the work stations.
The activities were being performed in accordance with the applicable drawings, weld data sheets, specifications, and instructions.
No violations or deviations were identified.
5.
Safety-Related Pipe Supports and Restraints The SRI reviewed S&W Specifications 228,312, " Field Fabrication and Erection of Pipe Supports ASME III, Code Classes 1, 2, 3 and ANSI B 31.1" and 228,310, " Design and Fabrication of Power Plant Piping Supports."
The SRI observed the installation of six safety-related pipe supports and reviewed the related documents.
No violations or deviations were identifie.
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Electrical System Installation The SRI has continued to observe the installation of the l'ower Generation Control Center equipment in the control rcom.
Review of the applicable inspection reports, inspection work sheets, etc.,
reveals conformance with the specified requirements of inspection plan, drawings, specifications, and instructions.
No violations or deviations were identified in this area of the inspection.
7.
Management Interviews The SRI met with one or more persons listed in paragraph 1 at various times during the inspection period. A meeting was conducted on April 29, 1983, to discuss the scope of the inspection and findings with those persons identified by an asterisk in paragraph 1.
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