IR 05000458/1982002
| ML20054G347 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/19/1982 |
| From: | Crossman W, Gilbert L, Hunnicutt D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20054G342 | List: |
| References | |
| 50-458-82-02, 50-458-82-2, NUDOCS 8206210468 | |
| Download: ML20054G347 (5) | |
Text
{{#Wiki_filter:. _ - - _ _ _ _ _ _ _ _ _ _ _ _ l . . . APPENDIX U. S. NUCLEAR REGULATORY COMISSION
REGION IV
Report: 50-458/82-02 Docket: 50-458 Category A2 Licensee: Gulf States Utilities Post Office Box 2951 Beaumont, Texas 77704 Facility Name: River Bend, Unit 1 Inspection at: River Bend Site Inspection conducted: April 19-23, 1982 Inspector: J////F '- L. D. Gilbeft, Reactor Inspector, Engineering Section Date Reviewed: ,,[[ N M gg,pg ,w' W. %. Crossmp, Chief, Reactor Project Section B D6te' 5//7/ 82 Appro[ved-D. M. Hunnicutt, Chief, Engineering Section Date' Inspection Summary Inspection on April 19-23, 1982 (Report 50-458/82-02) Areas Inspected: Routine, unannounced inspection of licensee action on previous inspection findings; site tour; review of quality assurance program for welding and nondestructive examination (NDE) of safety-related piping; and observation of work for welding of safety-related piping.
The inspection involved 34 inspector-hours onsite by one NRC inspector.
Results: Within the four areas inspected, no violations or deviations were identified.
l r206210468 820524 PDR ADOCK 05000458 G PDR
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. -2-DETAILS 1.
Persons Contacted Principal Licensee Personnel
- P. D. Graham, Director QA T. C. Crouse, Construction Superintendent R. Bailey, QA Engineer R. Kerr, QA Engineer, Management Analysis Corporation Stone & Webster (S&W) Personnel R. L. Spence, Superintendent, Field Quality Control (FQC)
A. Clawson, Inspection Supervisor J. Green, Inspection Supervisor R. Ferguson, QC Engineer R. Phebus, Senior Materials Engineer D. Whitlock, FQC Receipt Inspection D. Johnson, Piping Supervisor Other Personnel W. Calhoun, Senior Authorized Nuclear Inspector The NRC inspector also interviewed other licensee and contractor employees during the course of the inspection.
- Denotes those attending the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (50-458/81-08): Final weld reinforcement require-ments for weldolets.
The NRC inspector verified that the corrective actions required by Quality Assurance Finding Report (QAFR) No. 81-7-25 were com-plete for reinspection of previously installed weldolets and for providing additional training to pipe inspection personnel.
This item is considered resolved.
3.
Site Tour The NRC inspector toured the reactor building and auxiliary building for Unit 1 to observe construction in progress and to inspect housekeeping.
No violations or deviations were identifie. Safety-Related Pipe Welding and Nondestructive Examination a.
Review of Quality Assurance Program The NRC inspector reviewed the following S&W documents to assure that adequate controls have been established relative to welding and non-destructive examination of reactor coolant pressure boundary and other safety-related piping.
"QA Program Manual," Revision F - - " Quality Assurance and Control Manual ASME - Section III Division 1," Issued February 4, 1982 - Quality Standard Procedure 9.41, " Nondestructive Testing Program," No Revision, Change 3 - QA Directive Procedure 9.24, " Chemical Control of NDT Materials," Revision A, Change 1 QA Directive Procedures 9.31-RB and 9.32-RB, " Liquid Penetrant - Examination," Revision 0 QA Directive Procedure 9.41, " Radiographic Examination," - Revision B, Change 1 - Quality Standard Procedure 4.1, " Procurement Document Review (Site)," Revision A, Change 2 - Quality Standard Procedure 7.1, " Receiving Inspection," Revision D . Quality Standard Procedure 8.ll-RB, " Welding Material Control," - Revision 0 - Quality Standard Procedure 9.3, " Welding Procedure Qualification Program," Revision 0 - Quality Standard Procedure 9.31, " Welder / Welding Operator Qualification," Revision A, Change 1 - Welding Procedure W-3, "ASME III Welding Procedure," Revision 2 - Welding Technique Sheet W3-02, Revision 1 and Supporting Procedure Qualificaton Reports H80-25, H80-25-A, H80-25-E, H80-25-F, H80-26, H80-26-A, H80-26-B, H80-26-C, C81-1, C81-1-A, C81-2, C81-2-A, C81-1-B/C, C81-2-B, and C81-2-C l - Welding Procedure W-3-NSSS, "ASME III NSSS Piping System and Reactor Components Welding Procedure," Revision 0 !
-4-Welding Technique Sheet W3-NSSS-53, Revision 0 and Supporting - Procedure Qualification Reports C6-02, L9-02, and A9-06 In the areas reviewed, the above documents appeared to be adequate to control welding and nondestructive examination activities, b.
Observation of Work The NRC inspector observed the welding and quality control activities associated with fabricating the following safety-related piping welds: Weld Control Drawing System Class FW-002 1-CSH-004-B High Pressure Core Spray
FW-B6 1-RCS-900-B Reactor Coolant - Recirculation
FW-010 1-RHS-028-C Residual Heat Removal
FW-003 1-RHS-029-A Residual Heat Removal
In the areas reviewed, the entries on the weld data cards were con-sistent with the status of the welds, the inspections of FQC level 11 certified inspection personnel appeared to be adequate, filler materials were consistent with weld procedure requirernents and traceable to certified material test reports, and piping components were consistent with drawing material requirements and traceable to certified material test reports.
The NRC inspector determined, by interviewing construction personnel, engineering personnel, and FQC personnel, that the procedural reggire-ment of WTS W3-02 for preheating of weldments to a minimum of 200 F for P Number 1 carbon steel material over 3/4-inch to 1 1/2-inches thick and over 0.30% carbon may not have been accomplished since the carboncontentofthemateriglbeingweldedwasnotbeingcheckedby anyonetodetermineifg200 F minimum preheat would be required in lieu of the standard 50 F minimum preheat.
The materials inspected aboge were under 0.30% carbon for the thickness range requiring a 200 F minimum preheat for welding, therefore, the preheating require-ment of the procedure was not violated.
This is considered an unresolved item pending a review of all welded material to issure that no material has been installed which exceeded 0.30% carbon without the required minimum preheat.
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Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations.
An unresolved item related to preheating of weldments is discussed in paragraph 4.
6.
Exit Interview The NRC inspector met with P. D. Graham (Director QA) and A. B. Beach (NRC Resident Reactor Inspector) on April 23, 1982, and summarized the scope and findings of the inspection.
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