IR 05000458/1982006
| ML20062C043 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 07/15/1982 |
| From: | Crossman W, Hunnicutt D, Clay Johnson, Roberds M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20062C039 | List: |
| References | |
| 5-458-82-6, 50-458-82-06, 50-458-82-6, NUDOCS 8208050139 | |
| Download: ML20062C043 (7) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/82-06 Docket:
50-458 Category A2 Licensee:
Gulf States Utilities P. O. Box 2951 Beaumont, Texas 77704 Facility Name:
River Bend, Unit 1 Inspection At:
River Bend Site Inspection Conducted:
June 14-18, 1982 Inspector : b ^/P' 9 unnmd&
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,yvC. E. Johnsdn, Reactor Inspector, Engineering Section Date (Paragraphs 1, 2, 3, 4, 5, 6, and 7)
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7/W/R2-y s M. J. Roberds, Engineering Technician, Engineering Section
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(Paragraphs 1, 2, 4, 5, and 6)
Reviewed: W
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7/c/82.
W. A. Crossman, Chief, Reactor Project Section 8 Date Approved:
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D. M. Hunnicutt, Chief, Engineering Section Tate <
Inspection Summary Areas Inspected:
Routine, unannounced inspection of licensee action on previous inspection findings; review of quality assurance program for safety-related structural steel and supports; and observation of work for erection / installation and welding of safety-related structural steel and supports. The inspection involved 64 inspector-hours onsite by two NRC inspectors.
Results:
Within the three areas inspected, no violations or deviations were identified.
8208050139
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- P. D. Graham, Director QA
- T. C. Crouse, Construction Superintendent
- M. E. Walton, Assistant Project Engineer
- K. C. Hodges, QA Engineer
- I. M. Malik, QA Engineer Stone & Webster (S&W) Personnel
- R. S. Spence, Superintendent, Field Quality Control (FQC)
- E. A. Sweeney, Superintendent of Engineering
- J. P. Schippert, Senior Civil / Structural Engineer
- B. K. Pandit, Concrete Engineer The NRC inspectors 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 (0 pen) Deviation (50-458/81-10):
NRC Inspection Report 50-458/81-10 identified a deviation of cleaning practices for placement of concrete required by ACI 301.
The NRC inspector reviewed the corrective action taken by Gulf States Utilities (GSU).
GSU has issued a specification change which provides for Q-decking cleanliness criteria, which allows scattered sawdust, wood matches, nails, bolts, nuts, loose concrete, and coated welding electrodes to remain in the fluted portion of the Q-decking and scattered pieces of tiewire or nails to be left on the top of Q-decking ridges to receive concrete. However, this specification change is now in conflict with the River Bend Station FSAR which states, in part, that " concrete preparation, cleaning of construction joints, mixing and placing is equal to or exceeds the requirements of ACI 301 with certain exceptions which does not list Q-decking." The ACI 301 Code does not spell out cleanliness requirements specifically for Q-decking, but it does give cleanliness requirements for forms which concrete is to be placed.
Q-decking is a metal permanent form.
GSU has stated that they will submit an FSAR change to clarify the cleanliness requirements of Q-decking because they feel the ACI 301 Code does not specifically address Q-decking.
Pending the approval of the FSAR change, this item remains ope.
-3-(Closed) Violation (50-458/82-04):
NRC Inspection Report 50-458/82-04 identified an infraction concerning failure to follow storage procedures for structural steel fasteners.
An inspection of the safety-related storage conditions was made which revealed that storage conditions had not been met.
Bolt containers were filled with water and bolts had begun to rust.
Galvanized bolts and black iron bolts had not been segregated as required.
During the inspection conducted June 14-18, 1982, the NRC inspector inspected the storage conditions to observe the corrective action that had been imple-mented.
An enclosed corrugated metal building has been erected to house the fasteners.
The black iron and galvanized bolts were segregated as required.
Based upon the NRC inspector's review of this corrective action, this item is considered closed.
3.
Site Tour The NRC inspector toured the diesel generator building, the reactor building, the auxiliary building, and the control building for Unit 1 to observe construction in process and to inspect housekeeping.
No violations or deviations were identified.
4.
Review of Quality Assurance Implementing Procedures The NRC inspectors reviewed the following S&W documents to assure that adequate controls have been established relative to safety-related structural steel and supports:
Specification 219.710, Revision 3, October 20, 1980, " Shop
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Fabrication and Field Erection of Reactor Containment Vessel, Penetrations, and Hatches; Dry Well Head, Hatches, and Steel Plates; and Shield Building Hatches" Specification 229.160, " Major Mechanical Specification"
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Quality Standard (QS) 10.78-RB, Revision 0, April 8, 1982, (S&W)
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" Structural Steel Erection" QS-14.2, " Inspection Report System," Revision D, February 14, 1980
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Quality Assurance Directive (QAD) 10.5, Revision B, August 24, 1979,
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" Structural Steel and Rock Bolt Reinforcement Inspection "
QAD 14.1, " Inspection Report System"
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-4-Construction Methods Procedure (CMP) (S&W) 4.1-11.77, October 1977,
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" Structural Steel Erection" CMP 1.3, Revision B, November 13, 1981, " Storage and Maintenance of
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Equipment and Materials" CMP 1.8, Revision 0, May 18, 1981, " Control of Measurement and Test
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Equipment" CMP 1.11, Revision A, August 31, 1979, " Construction Control and
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Completion Program" CMP 4.2-8.76, " Installation of Category I Reactor Containment Liners"
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Graver's Nuclear QA Manual, " Field Activities Volume"
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R 1210310F0505, Revision D, Change 3, " Structural Steel / Welding
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Inspection Final"
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The above procedures reviewed appear to conform to the QA program as described in Chapter 17 of the FSAR.
No violations or deviations were identified.
5.
Observation of Work and Work Activities During the inspection, the NRC inspectors observed work and work activities in process in the auxiliary building and in the fuel building.
a.
Comnonent Supports The NRC inspectors visually inspected the work in process on residual heat removal (RHR) Heat Exchangers A, B, C, and D componant supports (upper and lower) in accordance with design drawing. Work observed was partially completed.
Final inspection had not been done.
The location and general appearance of the supports appeared as the design drawings indicated.
The NRC inspectors also observed support foundations for the RHR pumps.
b.
Structural Steel The NRC inspectors observed work performance and the erection and alignment of safety-related structural steel beams in the fuel building at elevation 125'-00".
Installation of the steel was in
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-5-compliance with CMP 4.1-11-77, " Structural Steel Erection."
Utilization of qualified NDE and inspection (FQC) personnel was adequate.
The FQC inspector observed by the NRC inspectors per-formed a thorough and adequate job.
No violations or deviations were identified.
6.
Review of QA Records / Documentation a.
Containment Liner Plate The NRC inspectors reviewed QA documentation on containment steel liner by Graver Nuclear, Inc.
The documentation was contained in a work package which was issued a unique number.
This unique numbering system was for each weld seam.
The seams were vertical or horizontal.
All documentation reviewed was readily retrievable and identifiable in accordance with the installation drawings.
Documentation reviewed contained the erection control sheet, record drawing, NDE reports, and radiographic reports.
Documentation reviewed was in compliance with Graver Nuclear QA Manual, " Field Activities Volume," and Specification 219.710.
The NRC inspectors also reviewed receiving and inspection documen-tation.
QA records reflected work accomplishments consistent with NRC requirements and SAR commitments.
Packages reviewed are listed below:
Traveler Package No.
247-3F 218-7F 246-4 218-8F 246-5F 218-9 246-6F 218-10F 246-7F 670F 218-6F 671F No violations or deviations were identifie.
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Structural Steel
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i The NRC inspectors reviewed the following drawings and inspection
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reports (IR) to verify compliance with applicable procedures,
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specifications, and commitments.
Documentation on structural steel
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is documented on the design drawings, and these drawings reference the IR.
Drawings I
Bristol Steel and Iron Works, Inc., Erection Drawing AE-9
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(Ref. Drawing 12210-ES-66C-8), " Floor Framing Plan and
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Details of Elevation 141'-0" in Auxiliary Building"
12210-ES-70K-6, Bristol Steel FE9, Revision 2, " Plates
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Inserts Details"
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I 12210-ES-62E-4, " Framing Plans, Elevations 125'-0" and
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131'-3" Inspection Reports on Erection of Structural Steel S2200947 - Bolting
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S2200700 - Bolting
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S2200204 - Bolting
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52200800 - Welding
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52200351 - Welding
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l 52200130 - Welding
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l No violations or deviations were identified.
c.
Component Supports I
The NRC inspectors reviewed documentation of component supports for
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the RHR heat exchangers and also documentation for various safety-related equipment foundation supports.
Records reviewed were
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j partially completed.
Documentation contained in the packages was in compliance with established procedures and requirements.
Documents i
reviewed are listed below:
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-7-Drawings Traveler Package No.
12210-EV-155A-4 1-RHS-Sup 1A-A (upper support)
12210-EV-1558-5 1-RHS-Sup 1A-B (lower support)
12210-EV-155C-3 12210-EV-1550-4 12210-EV-155E-2 Equipment Foundation Support 1-RHS-028-CDA (RHR pump)
1-RHS-107-CDA (RHR pump)
1-HVK *CHLl A (control room liquid chiller)
1-E22 *PC001 (HPCS pump)
1-G33 *PC0018 (reactor water cleanup pump)
1-HVK *PlD (chilled water pump)
No violations or deviations were identified.
7.
Exit Interview l
l The NRC inspectors met with licensee representatives (denoted in para-grapn 1) on June 18, 1982, to discuss the scope and findings of the inspection.
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