IR 05000458/1982004
| ML20042B827 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/10/1982 |
| From: | Crossman W, Hunnicutt D, Clay Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20042B825 | List: |
| References | |
| 50-458-82-04, 50-458-82-4, NUDOCS 8203260194 | |
| Download: ML20042B827 (5) | |
Text
.
.
APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-458/82-04 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, St. Francisville, Louisiana Inspection Conducted:
February 22-26, 1982 Inspector:
hl wwwbe#
S//o/82 C
C. E. Johnson, Reactor Inspector, Engineering Section
'Date
,
Reviewed:
IM e
.$ds47
///W. A. Crossmar., C.ief, Reactor Project Section B Date
)
Approved:
f)/ MenuJu#
8//O/f2.
,
D. M. Hunnicutt, Chief, Engineering Section 4) ate /
Inspection Summary Inspection on February 22-26, 1982 (Report 50-458/82-04)
Areas Inspected:
Routine, unannounced inspection of construction activities and observation of work activities related to structural steel and quality assurance for construction.
The inspection involved 34 inspector-hours by one NRC inspector.
Results:
In the areas inspected, one apparent violation was identified (Failure to Follow Storage Procedures for Structural Steel Fasteners -
paragraph 6).
8203260194 820311 PDR ADOCK 05000458 G
_ _ _ _
-_
- =-
.--
__
_.
L t
.
,
DETAILS i
1.
Persons Contacted
,
Principal Licensee Employees
- P. D. Graham, Director, Quality Assurance
- K. C. Hodges, QA Engineer
- I. M. Malik, QA Engineer
- M. A. Walton, Assistant Project Engineer
'
- R. B. Stafford, Supervisor, Quality Assurance
- T. C. Crouse, Superintendent, Site Construction Stone and Webster Personnel i
- B. R. Hall, Senior Field Quality Control (FQC) Engineer W. Turner, Senior FQC Inspector D. Scheele, FQC Engineer B. Bolick, FQC Inspector
,
The NRC inspector also contacted other licensee and contractor personnel
]
during the inspection.
J
- Denotes those attending the exit interview.
2.
Site Tour The NRC inspector toured the Reactor Building, Auxiliary Building, Fuel
!
Building, and Control Building to observe construction in progress and to inspect housekeeping.
General construction practices were observed.
No violations or deviations were identified.
I 3.
Review of FQC Procedures / Specifications The NRC inspector reviewed several procedures and specifications during the course of the inspection.
These instructions and procedures appear to conform to the facility's QA program as described in Chapter 17 of the Gulf States Utilities' FSAR.
These instructions and procedures specify the attributes that must be accomplished by the FQC inspectors in order to perform a satisfactory inspection.
These attributes vary
!
depending on the type of inspections conducted, such as structural steel erection or inspection of high strength bolting.
Instruction /
procedures reviewed are listed below:
Quality Standards (QS) 14.2, Revision D, " Inspection Report System" QS 15.1, Revision A, "Nonconformance and Disposition Report"
,
i
.-
-. --
,,
- - -.
-
..
.-
.-
_ -
.
QCI-FRl-D2.5, " Indoctrination and Training of FQC Personnel" QS 10.17, Revision A, " Structural Steel Erection" CMP 4.1, " Structural Steel Erection" CMP 6.2, " Structural Welding" CMP 6.9, " Welder Qualification Specification 210-310, " Structural Steel Erection" Specification 210-320, " Miscellaneous Steel and Embedments -
CAT I" QS-13.ll, Revision A, " Material / Equipment Storage" Cooper / Turner Inc., Manufacturers Instruction Manual, " Load Indicating Washers (Coronet)"
R 1210310F0501, Revision C, " Structural Steel / Receipt Inspection" R 1210310F0502, Revision E, " Structural Steel / Structural Jteel Erection" R 1210310F0504, Revision F, " Structural Steel / Inspection of High Strength Bolting R 1210310F0505, Revision 0, "Structura) Steel / Welding Inspection Final" Specification 229.170, " Storage and Maintenance of Permanent Plant Equipment" No violations or deviations were identified.
4.
Observations During the inspection, the NRC inspector observed two activities in the Reactor Building which were in progress - concrete placement and structural steel erection.
a.
Concrete Placement The NRC inspector observed the placement of RB-3-W-220.
During this concrete placement, the NRC inspector noticed during consolidation of concrete that one workman allowed a vibrator to remain immersed in the concrete longer than required.
This was an isolated case and was immediately corrected by the FQC inspector at the placement.
No segregation of concrete was observed.
_
.
_.
.
.
b.
Structural Steel Erection The NRC inspector observed ironworkers placing restraint beams 1-139B and 1-13983 around the Reactor Building shield wall at approximately elevation 141'00".
These beams appear to conform to Bristol Steel Drawing FE0174, Sheet KE-20.
No violations or deviations were identified.
5.
Review of Records / Documentation a.
Receiving and Storage The NRC inspector reviewed inspection reports (irs) for receiving and storage of four pipe restraints and their respective lugs.
These items were fabricated by Teledyne-Brown Engineering.
All requirements
'
were checked off by the FQC receiving inspector, initialed, and dated.
Nonconformance and dispositions reports (N&Ds) were referenced on the IR on nonconforming items.
Restraints and irs reviewed are listed i
below:
irs Restraints M1100060 1-MSS-PRS-804 P1100168 1-MSS-PRS-824 M110060 1-MSS-PRS-803 M110060 1-MSS-PRS-P23 b.
FQC Structural Steel The NRC inspector reviewed documentation on many structural steel items inside the containment.
All documentation for structural steel was recorded on irs and directly on the design drawings.
The design drawings referenced the IR on which the item was documented.
Color codes were utilized by FQC structural inspectors.
All FQC inspectors used the same color codes on the master drawing.
Some color codes were for the erection of steel, bolted connections, and welding of joints.
The irs were forwarded to the vault after the inspection.
Each design drawing is maintained until all structural items are completed on that drawing, then the drawing
>
is forwarded to the vault.
No violations or deviations were identified.
-
,
,
.
_
. -
. -.
.
_ - -
_ _ __
.
..
..
,. _.
- - - _ - - _ -.- -
.-.
--
- - -
. _ -
.-
. -.
._-.
- - -.
_
i Ir j
.
.
I I
6.
Inspection of Structural Steel Storage Conditions (Category I)
i I
The NRC inspector inspected storage conditions of safety related struc-t tural steel.
During the inspection of the storage yard, the NRC inspector observed that structural beams and structural shapes were stored as required by Specification 210.310, " Structural Steel," and ANSI 45.2.2.
Steel members were elevated off the ground on pallets.
Storage conditions appear to be adequate for beams and structural shapes.
However,in the
,
,
section where safety-related bolts and nuts were located, the conditions j
were not adequate.
Most of the bolts had been exposed to moisture; in some cases, water had accumulated to the top of the buckets in which the
bolts were contained.
Some bolts had begun to rust.
Bolts were not
'
segregated; i.e., galvanized and black iron bolts were intermixed.
.
These storage deficiencies were also observed by a GSU representative I
who accompanied the NRC inspector.
Inspection Report No. 52200482 was generated by Stone and Webster after this inspection.
Corrective action was initiated immediately after the inspection identified these storage i
deficiencies.
These storage conditions were not in compliance with
'
Criterion XIII of Appendix B of 10 CFR Part 50 and Stone and Webster Specification 210.310.
This is a violation.
(458/8204-01)
7.
FQC Personnel Qualification (Structural)
,
The NRC inspector reviewed the FQC Personnel Qualification Matrix.
All
,
FQC inspectors observed during this inspection period were qualified to perform that specific inspection.
The NRC inspector discussed procedural requirements with the structural FQC inspectors.
All FQC inspectors i
j interviewed appeared to have adequate knowledge of procedural requirements.
No violations or deviations were identified.
!
8.
Exit Interview l
The NRC inspector met with licensee representatives (denoted in para-
graph 1) on February 26, 1982, to discuss the scope and findings of l
the inspection.
i
!
i
,
.
-,,
.,.., - - - -,
-- -
,
rw
- - - - - -y,---_-,-----,-.,,y.,-_-,cm
--y~4m.
- -__.... -.
- -_
-, -,.
--
-4,
--,---%m..
.
,,---.---vm