IR 05000458/1983009
| ML20023B538 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 04/20/1983 |
| From: | Brown R, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20023B531 | List: |
| References | |
| 50-458-83-09, 50-458-83-9, NUDOCS 8305050163 | |
| Download: ML20023B538 (8) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-458/83-09 Docket: 50-458 Permit: CPPR-145 Licensee: Gulf States Utilities (GSU)
P.O. Box 2951 Beaumont, Texas 77704 Facility Name: River Bend, Unit 1 Inspection At: River Bend Inspection Conducted: March 5,1983, through April 6,1983
E' 3 Inspector:
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R. L. Brown, Senior Resident Inspector Date
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9 don 3 Approved:
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W. A. Crossman, Chief Date Reactor Project Section B Inspection Summary Inspection Conducted March 5,1983, through April 6,1983 (Report 50-458/83-09)
Areas Inspected: Routine, announced inspection by the Senior Resident Inspector (SRI) including site tour; licensee identified construction deficiencies; containment structural concrete; storage of safety-related pipe and valves; reactor coolant pressure boundary piping installation; structural steel installation; reactor vessel and internals storage; containment vessel steel structure. The inspection involved 127 inspector-hours by one NRC inspector.
Results: Within the eight areas inspected, no violations or deviations were identified.
8305050163 830421 PDR ADOCK 05000458 G
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-2-DETAILS 1.
Persons Contacted Principal Licensee Employees (GSU)
P. D. Graham, Director, Quality Assurance R. B. Stafford, Supervisor, Quality Assurance
- M. A. 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, QA Engineer
- D. G. Seymour, QA Engineer
- C. L. Ballard, Supervisor, Quality Systems P. J. Dautel, Licensing Staff Assistant
- 0. DeMiranda, QA Engineer 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, Elec+rical 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 D. M. Cowart, FQC Senior Inspector D. Scheele, FQC Supervisor The 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 areas of the site during the inspection period to observe construction progress, general job practices, housekeeping, and fire protection.
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Follow Up On Licensee Identified Deficiency Reports,10 CFR 50.55 (e)
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(Closed) Deficiency Report (DR-81/GSU letter RBG-13885) " Improper 0-Ring Material used in Gould Supplied Pumps." The SRI reviewed the S&W N&D 2991 that describes a problem with eight pumps supplied by Gould Company where the 0-ring gasket mater.ial was found to be Teflon which was not allowed by S&W Specification 237,160.
S&W Interoffice Memorandum, date January 26,1983, " Evaluation of a
. Problem Use of Teflon 0-Rings by Pump Vendor," states in part, that the fluids being pumped by the pumps are non-radioactive, and therefore will not produce radiation-induced Teflon degradation and no detrimental effects would have developed had the Teflon 0-rings not been discovered.
S&W letters RBS-8292 to GSU states, based on the above evaluation, they conclude that the problem is not reportable under 10 CFR 50.55(e)
requirements.
GSU Memorandum RBG-14,271 states that GSU engineering and QA concurs with the S&W conclusions stated in RBS-8292.
-f The SRI concurs that the problem is not reportable pursuant to 10 CFR 50.55(e).
This item is closed.
(Closed) Deficiency Report (DR-90/GSU letter 14,034) Incorrect Size of Structural Steel Connection Plate.
The SRI reviewed N&D 3070 and E&DCRP-2147A that describes the problem and corrective actions.
S&W letter RBS-8269 to GSU states that the design of the connection with three bolts in lieu of four bolts results in an overstress of approximately 20 percent, the allowable stresses upon which the design is based have a safety factor of 2.0.
Hence, the beam would still perform its intended function, and therefore is not reportable under 10 CFR 50.55(e).
GSU Memorandum RBG-14,211 states GSU engineering and QA concur with the evaluation presented in S&W letter RBS-8269.
The SRI concurs that the problem is not reportable under 10 CFR 50.55(e).
This item is closed.
(Closed) Deficiency Report (DR-7/GSU letter RBG-6964) " Nondestructive Testing performed by CBIN."
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-4-(Closed)' Deficiency Report (DR-9/GSU letter 6922) " Surface Condition of
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(Closed). Deficiency Report (DR-il/GSU letter 6923) " Improper Repair of Cadwelds."~
The SRI was informed by GSU that the above three' deficiency reports have not been closed by the NRC.
The SRI reviewed IR79-05 that ' identified these conditions as unresolved items.
It appears that as a result of this inspection GSU submitted these potential deficiency reports.
The SRI reviewed IR80-01 that closed all three of these unresolved items, therefore, these deficiency reports are considered to be closed.
4.
Storage of Safety Related Manual and Motor Operated Valves and Pipe
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The SRI observed small and large bore pipe and valves stored throughout the reactor and control buildings.
Most of the large bore is in temporary hangers and all caps and plugs are in place.
The large bore valves are stored on plywood. The MOVs are stored with the valve stem and motor shaft in a horizontal position and activator limit' switch compartment cap in a vertical position.
The storage of these items appears to be in accordance with Specification No. 229,170," Storage and Maintenance of Pennanent Plant Equipment."
No violations or deviations were identified in this area.
5.
Reactor Coolant Pressure Boundary Piping Installation Inside Containment The SRI observed the installation of the following piping systems within the outermost isolation valves: Main steam, feedwater and residual heat removal.
The SRI reviewed the applicable drawings, specifications, procedures, instructions, and quality records related to these systems and determined that the installations were as specified.
No deviations or violations were identified in this area.
6.
Structural Steel Installations Outside Containment The SRI reviewed S&W Specification 210,310, " Structural Steel," that establishes the steel erection requirement.
-5-The SRI observed FQC inspection of erected fuel building and auxiliary building structural steel and reviewed quality documents related to these activities.
No violations or deviations were' identified in this area.
7.
Stored Reactor Vessel and Reactor Vessel Internals The SRI observed the transfer of reactor vessel (RV) closure head and
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the RV_ internal components (e.g., separator. and dryer) refueling platform, etc., from the warehouse storage to refueling storage areas at the 162' and 186' elevation. The handling of these items appeared to be in accordance with the requirements and good practices.
Except for the refueling platform, all items were properly-stored in their assigned area.
The SRI also observed that the protective covers were in place on the RV openings and the controlled circulating heated air is being maintained as required by Specification 229,170.
No violations or deviations were identified.
8.
Containment Vessel Steel Structure The SRI observed the joint fit-up of the torispherical dome to the cylindrical shell section of the containment vessel.
The SRI also observed welder training, using the automatic welding machine to be used in making the above joint weld.
GSU notified the NRC of indications found by ultrasonic examination in the containment vessel dome lifting lugs areas (DR-103).
No violations or deviations identified.
9.
Containment Vessel Structural Concrete An accident occurred while the Lampson Transi-Lift crane was lifting the 400-ton form assembly for the containment shield building roof.
The form consisted of sheet metal decking and reinforcing bar supported by structural steel ribs and circumferential members. The form had been assembled on the ground and was being lifted to the top of the cylindrical containment shield building, after which concrete would have been poured to form the shield roof.
The same procedures were being followed with this lift as on the previous night when the lh-inch thick steel containment building
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-6-dome-(500-t'on) had been successfully lifted and placed on the containment building by the same crane without mishap or problem.
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The form was lifted to about 30 feet above its assembly area and was
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about to be moved to position for lifting and placement on the shield building. At that point, people heard metallic noises and observed water (rain water ' collected in upper parts of the crane) falling. The crane mast buckled, the shield form fell to the ground and the crane collapsed.
Fortunately, no one was. seriously injured and only vehicles and temporary buildings were damaged.
Except for the shield form, no permanent structures or equipment were damaged.
.The cause of.the accident is undetermined.
It could be due to a structural or mechanical failure in the crane, to misoperation, to failure of the cribbed roadway, or to wind interaction or other unknown cause. GSU, Stone & Webster, Lampson, and the insurance companies have experts studying all of these possibilities.
Stone & Webster is studying the repair and salvage potential of the damaged form and is considering means of erecting repaired sections in place on top of the containment shield.
GSU has submitted a' potential deficiency report -(DR-104) to the NRC.
10.
Management Interviews The SRI met with one or more persons listed in paragraph 1 at various
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times during the inspection period. A meeting was conducted to discuss the scope of sthe inspection and findings with those persons identified by_ an asterisk in paragraph T l
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