IR 05000458/1982016
| ML20028E996 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 01/05/1983 |
| From: | Brown R, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028E994 | List: |
| References | |
| 50-458-82-16, NUDOCS 8301280329 | |
| Download: ML20028E996 (7) | |
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l APPENDIX i
U. S. NUCLEAR REGULATORY COMMISSION
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REGION IV
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Report: 50-458/82-16
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Docket: 50-458 Licensee:
Gulf States Utilities (GSU)
P.O. Box 2951
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Beaumont, Texas 77704
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i Facility Name:
River Bena, Unit 1
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Inspection At:
River Bend i
Inspection Conducted:
November 1, 1982 through December 15, 1982
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Inspector
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fh-RossL. Brown,SeniorResidentInspector Date Approved:
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W. A. Crossman, Chief Date Reactor Project Section B Inspection Summary i
Inspection Conducted November 1, 1982-December 15, 1982 (Report 50-458/82-16)
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Areas Inspected:
Routine, announced inspection by the Senior Resident
Inspector (SRI) including site tour; follow up of previous inspection i
findings; ifcensee identified construction deficiencies; electrical cable and
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raceway installation; containment penetration welding; and electrical systems installation.
The inspection involved 121 inspector-hours by the NRC Resident Inspector.
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Results: Within the areas inspected, no violations or deviations were Identified.
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l, 8301200327 830110 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
- K. C. Hodges, NRC Compliance Coordinator, Quality Assu. ance M. A. Walton, Superviscr. Site Engineering W. J. Reed, Director, Nuclear Licensing (Beaumonti L. A. England, Lead Licensing Engineer (Beaumont)
R. J. King, Licensing Engineer (Beaumont)
V. J. Nonnand, Construction Supervisor G. R. Kimmell, QA Engineer
- D. G. Seymour, QA Engineer
- C. L. Ballard, Supervisor, Quality Systems
- R. G. West, Engineering
- W.
S. Stuart, Area Coordinator Stone and Webster
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- 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 Supervi or, Electrical A. Clawson, FQC Inspection Supervisor D. Whit *iock, FQC Inspector Supervisor J. H. Raft, Senior Construction Supervisor, Electrical C. A. Goody, Resident Manager E. A. Sweeney, Superintendent, Engineering G. M. Byrnes, FQC Assistant Superintendent V. L. Barton, FQC Inspection Supervisor _
- W. I. Clifford, Senior Construction Manager
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- F. A. Canuso, Project Engineering Assurance Engineer
- J. J. Zullo, QA Program Administrator
- R. J. Beaudet, iQC, Inspection Supervisor
- R. L. Whitley, FQC Assistant Superintendent The SRI alsc interviewed additional licensee, Stone and Webster (S&W),
and other contractor personnel during this inspection period.
- Denotes those persons that attended the management interview.
2.
Site Tour The SRI toured most areas of the site during the inspection period to, observe construction progress, general job practices, housekeeping, and fire protection.
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3.
Licensee iction on Previous Inspection Findings (Closed) Violation (50-458/82-03)
" Inadequate Procedural Requirements to Ensure Adequate Storage and M51ntenance of Safety-Related Equipment."
The SRI reviewed the following documents to verify implementation of the correctiva actions and preventative measures.
a.
Specification 229.170, " Storage and Maintenance of Pemanent Plant Equipment," has been revised to' include an index that identified the equipment and specifie; the storage requirements and inspection frequency.
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b.
Equipment storage history cards (ESHC) are prepared by the site engineering group (SEG) and include the storage requirements and inspection frequency.
c.
Completed ESHC's indicate that the storage and maintenance require-ments are bung met and tne items are oeing signeu-off as complete and acceptable by the responsible person, and at the specified frequency.
This violation is considered closed.
(Closed) Deviation (50-458/82-03)
"FSAR Requirements for Analysis and Design of Pipe Supports." The SRI reviewed the GSU Quality Assurance Procedure, QAP-3, Revision 2, " Design Control," that assigns the respon-sibility for design control during design and construction to the major contractors.
It also states that GSU performs a technical review of selected design documents generated by the major contractors. The procedre further states that GSU quality' assurance verifies major con-tractor compliance with program requirements through periodic audits and surveillance.
The S&W Engineering Assurance Procedure, EAP-3.1, Revision 2, "Verifi-cation of Nuclear Power Plant Design," defines a design control method that provides for design analysis, such as physics, stress, material acceptability, etc.
The SRI reviewed GSU Audit Report GSU-SWC-10/82, for their audit of, S&W, Cherry Hill Operatici Center.
One of the areas-covered during this audit was design control (electrical). This audit verified'that GSU and S&W are in conformance with their quality program requirements.
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The SRI also reviewed the following documents related to the testing perfonned to detennine material acceptability;- engineering established hardness testing procedure (including acceptance criteria), hardness test results, comparison tensile test results of testing originally perfonned by the tube manufacturer, and retests by an independent test laboratory at a later date (1 to 2 years) of five heats of A500 Grade B material that represents the steel supplied to River Bend Station (RBS) by Bergen Patterson. These test results indicate that the A500 Grade B tube steel used at RBS has a minimum elongathn of 12% after strain aging. '
This item is considered closed.
4.
Follow Up on Licensee Identified Defic'iency Reports (Closed) Deficiency Report (DR 39/GSU letter RBG 12,255)
" Inadequate Gap Between Drywell Beam and Drywell." The SRI reviewed bnconformance and Disposition Report (N&D) 2205 that defined the rework required to correct the discrepancy and field quality control (FQC) sign off verifying completion of the rework. Also, Engineering and Design Coordination Re-port (E&DCR) C-4102 adds to Specification 210.310 an inspection hold point ud requires 100% inspection by FQC of beam end gaps for all sliding connections.
This item is considered closed.
(Closed) Deficiency Report (DR 66/GSU letter RBG 13,173)- " Linear Indi-cation in RHR System Heat Exchanger Supports by Teledyne Brown."
The SRI reviewed the following related documents:
N&D 2709, SitW 1etters RBS 7954 and RBS 8067 to GSU, and GSU memorandum RBG 13,653. The SRI concurs that the condition was not reportable.
(Closed) Deficiency Raport (DR 24) " Defective Rosemount Transmitter and Trip Units for Reactor Vessel Water Level Scrains.
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Company (GE) letter MFN-200-81, states that GE letter MFN-154-81 to NRC Headquarters, Reportable Condition per 10 CFR Part 21, erroneously included River Bend GSU as being one of the affected plants. This item is considered closed.
(Closed) Deficiency Report (DR 43/GSU letter RBG 12,393)
" Unsatisfactory Inspection Performed by an FQC Inspector." mThe SRI reviewed the Report of a Problem RB-FQC-002 that describes how the condition was found and the apparent. time period of the deficiency and the FQC investiga-tion report that identified the unsatisfactory welds that were accepted by the identified inspector during December 1581, January, February, and March 1982; FQC records show that inspections conducted by this ' specific inspector during December 1981, and January, February, and March 1962, were reinspected to identify any necessary corrective action. All non-
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confonnances that were identified were reworked.
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The investigation revealed that this problem was an isolated case confined to a specific individual and a specific time period and did not represent a lack of understanding of the requirements. This item is considered closed.
(Closed) Deficiency Report (DR 70/GSU letter RBG 13,270 and Trans-america Delaval 10 CFR Part 21 reports to NRC dated June 23, 1982, and July 13, 1982)
" Improper Material in Generator Governo: Coupling Drive Element." The SRI reviewed the letters of notification to the NRC and S&W letter RBS-8040 to GSU that describes the safety' implications as a significant deviation from performance specifications and S&W N&D 2810 that requires the replacement of all the governor coupling drive elements and verification by FQC. This item is considered closed.
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(Closed) Deficiency Report (DR 22/GSU letters -RBG 11,438 and RBG 11,622, and DR 38/GSU letter RBG 12,169)
" Spring Nut Slippage.(DR 2')" and
"PS-10RS Spring Nuts Performance Failure (DR 38)." The SRIc reviewed N&D 1933 that described the original deficiency and corrective action (DR 22).
However, as the recommended replacement nuts were being installed, it was'
noticed that the nuts being installed were different from those tested in November 1931. This difference resulted'in the' generation of N&D 2198..
N&D 2198 states, remove the spring nuts presently installed in embedment PS-280ST and replace them with improved PS-9227RS spring nuts'that are
dichromated gold for easy identification. The rework'specified in this.
N&D has been completed, inspected, and accepted by quality control. This item is considered to be closed.
5.
Electrical Cable and Raceway Installation a.
Cable Installation
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The SRI observed the pulling operation of three Category.2 and two Category 1 cables. The electricians were observed to use lubricant gel, pully, etc., to reduce friction during the cable pulls.
The SRI also reviewed rix cable pull tickets and six QA surveillance -
inspection reports for Category 2 cable. pulling operations.
The cable pulling operations appear to be in conformance with-the requirerents of Inspection Plan R 1248000F0518 and Specification 248.000.
No violations or desiations were ~ identified in this area.
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Raceway Installation The SRI visually examined approximately 500 feet of the installed QA Category 1 cable trays.
The SRI also reviewed five raceway tickets and two QA inspection reports.
The activity appears to be in conformance with the requirements specit'.ed in Inspection Plan R 1348000F0507, Revision E, and Speci-fication 248.000, Revision 5.
No violatiens or deviations were identified in this area.
6.
Containment Penetration Welding The SRI has continued to observe the welding and weld control activities associated with the installation and welding of the equipment hatch frame in the containment vessel.
In the area reviewed for these welds, it appears the activities are in conformance with the specified requirements.
No /iolations or deviations were identified in this area of the inspection.
7.
Electrical Systems Installation The SRI has continued to observe the installation of the PGCC equipment
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in the control room.
Review of the applicable inspection reports, inspection work sheets, etc.,
reveals conformance with the specified requirements of inspection plan, drawings, specifications, and instructions.
No violationc or deviations were identified in this area of the inspection.
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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 December 15, 1982, to discuss the scope of the inspection and findings with those per-sons identified by an asterisk in paragraph 1.
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