IR 05000458/1981013
| ML20041A513 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 01/26/1982 |
| From: | Beach A, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20041A506 | List: |
| References | |
| 50-458-81-13, NUDOCS 8202220245 | |
| Download: ML20041A513 (7) | |
Text
,
-
.
o
.
APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Repor.':
50-458/81-13 Docket:
50-458 Licensee:
Gulf States Utilities Post Office Box 2951 Beaumont, Texas 77704 Facility Name:
River Bend, Unit No.1 Inspection at:
River Bend Site Inspection Conducted:
November 16 through December 31, 1981 ahim 1/9Ak Inspector:
aar A. B.'B'each, Resident Reactor Inspector Dite'
//24[82 Approved:
e W. A. Crossman, Chief, Projects Section 3 Date Inspe;. tion Summary:
Inspection During November and December (Report No. 50-458/81-13)
Areas Inspected: Routine, announced inspection by the Resident Inspector (RRI)
TdEluding follow up of previous inspection findings; follow up of licensee identified items; concrete placement activities; welding of safety-related piping; safety-related piping support and restraint installation; structural steel erection; and Class IE electric equipment qualification. The inspection involved 112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br /> by one NRC inspector.
Results: Of the six major areas inspected, no violations or deviations were identified.
8202220245 820203
] DR ADOCK 05000j58
-
-
.
.
..
1.
Persons Contactad, Principal Licensee Employees
- P. D. Graham, Director, Quality Assurance C. L. Ballard, Supervisor, Quality Assurance R. B. Stafford, Supervisor, Quality Assurance G. V. King, Supervisor, Quality Assurance T. C. Crouse, Superintendent, Site Construction M. A. Walton, Director, Site Engineering W. J. Reed, Director, Nuclear Licensing Stone and Webster Personnel C. D. Lundin, Manager, Project Quality Assurance R. L. Spence, Superintendent, Field Quality Control (FQC)
G. M. Byrnes, Assistant Superintendent, FQC J. D. Davis, Assistant Superintendent, FQC R. L. Whitley, Assistant Superintendent, FQC W. I. Clifford, Senior Resident Manager-C. A. Goody, Resident Manager E. A. Sweeny, Superintendent of Site Engineering P. D. Hanks, General Superintendent, Construction D. P.'Barry, Superintendent, Construction Services The RRI also interviewed additional licensee, Stone and Webster, and other contractor personnel during this inspection period.
- Denotes those persons with whom the RRI held on-site management meet-ings during this inspection period.
2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (50-458/80-02): Compliance with ASME Certification System Requirements.
The ASME site survey has been performed. How-ever, this item will remain open until the Certificate of Authorization is received.
(0 pen) Unresolved Item (50-458/81-08): Finished Weld Profile Require-ments for Weldolets.
This item will be closed pending regional review of completed actions required by Quality Assurance Finding Report
- 81-7-25-B.
(Closed) Unresolved Item (50-458/81-09):
Reportability Requirements Relative to the Use of ASTM A 500 Grade B Material. This matter was upgraded to a deviation in NRC Inspection Report 50-458/81-10; specifically,
" Failure to Promptly Report a Potential Deficiency in Accordance with Previous Licensee Commitments." Thus, this unresolved item is considered close F
-
.
.
.
,
(Closed) Violation (50-458/80-12):
Insufficient Lighting of Concrete Placement.
Discussions with Field Quality Control (FQC) personnel confirmed their responsibility to assure that lighting in concrete place-ments is adequate to assure proper placement and inspection. A selected review of several concrete placements, including the Reactor Shield Building placement referenced in paragraph 5, illustrated the use of adequate lighting to ensure proper placement and inspection techniques.
Thus, this matter is considered closed.
(Closed) Violation ( 50-458/80-12): Water / Cement Ratio Exceeded the Maximum Allowable.
Corrective action has been achieved in accordance with the licensee's response to this violation. A review of concrete placement records has indicated this to be a relatively isolated occurrence. Thus, no further action is necessary and this matter is considered closed.
3.
j.icensee Identified Construction Deficiency Reports (Closed) Overturning of the Primary. Shield Wall. On January 25, 1981, at approximately 3:30 p.m., while being moved on its transporter, the primary shield wall sustained damage when the transporter overturned.
On January 29, 1981, the Gulf States Utilities Quality Assurance Director reported, in a memorandum to the Executive Vice President, the results of his investigation to determine the circumstances contributing to the primary shield wall accident. These results were documented in NRC In-spection Repert 50-458/81-01.
In summary, interviews were conducted to establish facts related to the incident.
From these interviews, it was determined that the primary-shield wall (pSW) was apparently moved without appropriate notifications,
"at the whim of the rigging supervisor." Since Stone and Webster had never accomplished a move of equipment of this vertical height, it was also determined that site management should have been more involved in the move.
The investigation report also included a review of procedures and drawings for the transport of the shield wall to the designated work area. The review of procedures included an evaluation for adequacy and implementation.
The licensee reported this incident to the NRC Region IV office in accord-ance with the requirements of 10 CFR 50.55(e).
In a letter to the NRC Region IV office dated June 23,1981,(RBG-10618),
the licensee summarized the final results of his investigation con-cerning this reportable deficiency. As stated in this letter, the principal area of damage was limited to the base plat r-
-
.
.
.
This area has been reworked and repaired. An engineering evaluation was performed concluding that the impact due to the accident "did not affect the structural integrity of the shield wall."
Thus, since repairs have been completed and the legal requirements of 10 CFR 50.55(e) have been satisfied, this matter is considered closed.
(Closed) Crane Falling into Reinforcing Steel in Cooling Tower.
Gulf States Utilities has reviewed the incident involving a crane boom falling on the number one cooling tower which was reported to the NRC Region IV office April 21, 1981, as a potential deficiency that may meet the requirements of 10 CFR 50.55(e). The evaluation determined that the incident does not meet the reporting requirements as the evaluation and the repair required is not extensive. The damage was found to be isolated to reinforcing steel only.
A Nonconformance and Disposition Report (N&D 1213) was initiated. A review of this N&D indicated there to be no damage to any applicable portion of the east wall of the cooling tower. Thus, this matter is considered closed.
On December 21 and 22, 1981,.the NRC inspector reviewed records and procedures relative to 10 CFR 50.55(e) reporting at the corporate office of Gulf States Utilities. This review was performed at the cor-porate office as licensee management perceives "reportability" to be a licensing function.
Processing of changes to the Final. Safe y t
Analysis Report (FSAR) was likewise reviewed.
No violations or deviations were identified.
4.
Site Tours The NRC inspector toured the safety-related plant areas several times weekly during the. inspection period to observe the progress of con-struction and the general practices involved. Housekeeping, document control, and weld rod control were specifically reviewed.
No violations or deviations were identified.
5.
Concrete Placement Activities The NRC inspector toured the batch plant facility during the inspection period. The Stone and Webster on-site testing laboratory was likewise toured and activities with regard to concrete testing were observed.
All activities observed were found to be in accordance with specification requirement I
.
..
.
The NRC inspector observed Shield Wall placement RB3-W190(7126),
Mix A3-G, on December'9, 1981.
Specifically noted during the placement were insepection techniques of Field Quality Control personnel, con-sistency of placement, coordination of the Batch Plant with the place-ment activity, and the consolidation techniques of construction personnel.
The placement observed exhibited good planning and production efforts.
All activities observed during the placement indicated that the concrete was placed in accordance with the appropriate specification requirements.
No violations or deviations were identified.
6.
Welding of Safety-Related Piping Shop fabrication and field erection of safety-related piping at the River Bend site is well underway.
As discussed in NRC Inspection Report 50-458/80-13 (paragraph 5), and NRC Inspection Report 50-458/81-09 (paragraph 7), the site weld-to weld reject rate remains rather high.
The licensee is continuing to take and evaluate courses of action necessary to achieve as low as possible weld-to-weld reject rate.
(Ihese actions were discussed in NRC Inspection Report 50-?58/81-10, paragraph 6).
Welding of safety-related piping is now in full progress, and five per-cent of the safety related welds have now been completed.
The NRC intpector is closely monitoring welding activities and several field welds were observed at different stages during this inspection period.
Although all activities were observed to be in accordance with specifi-cation requirements, the weld-to-weld reject rate has not improved.
The NRC inspector will continue to closely monitor welding activities.
No violations or deviations were identified during this inspection period.
7.
Safety-Related Piping Support and-Restraint Installation The NRC inspector reviewed Stone and Webster Specification 228.312,
" Field Fabrication and Erection of Pipe Supports, ASME III, Code Classes 1, 2, and 3, and ANSI B31." This specification establishes the installation requirements for safety-related pipe supports.
In addition to this review, procurement requirements for ASTM A 500-Grade B steel used for structural tubing were discussed with licensee representatives. This subject was documented as an unresolved item in paragraph 8 of NRC Inspection Report 50-458/81-10, and still remains open.
In this regard, the licensee has requested an interpretation from the American Society of Mechanical Engineers concerning the requirements of the ASME Boiler and Pressure Vessel Code,Section III, Division I, NCA-4000 Quality Assurance NF-2610 Documentation and Maintenance of Quality System Progra r
-
.
.
.
Specifically, an N-type Certificate Holder's Quality Assurance Program (NCA-4000) allows the establishment of a Qualified Vendor List (QVL).
In order to place a vendor on the QVL, the vendor completes a questionnaire which is evaluated by the Certificate Holder, including Quality Assurance personnel.
The infonnation provided is not verified.
Additionally, a review of the vendor's historical perforniance is completed.
" Historical Performance" is based on whether or not the Certificate Holder is aware of any problems with the material in industrial application.
Vendors that are placed on the QVL are not audited or surveyed.
In order to assure compliance with the provisions of NF-2610 when pro-curement is made from QVL vendors, the Certificate Holder employs an
" evaluation of the material upon receipt by the Certificate Holder."
The evaluatiore consists of verification at receipt inspection that the material markings' correspond with the original material manufacturer's material test reports, and that these material test reports comply with the material specification. Additionally, limited " random" (not statistically based) confirmatory testing of material (one piece per vendor per year) is performed.
The licensec is currently awaiting a response to this request for inter-pretation.
The NRC inspector has sent a letter to the NRC Region IV office in order that these procurement practices may be further re-viewed to determine if they are, in fact, in accordance with the require-ments of Appendix B to 10 CFR 50.
No violations or deviations were identified.
8.
Structural Steel Erection The NRC inspector reviewed storage conditions for the structural steel, especially A 325 bolts and washers.
Segregation was noted to be a concern, and licensee management took immediate action to assure se-gregation requirements were met. Subsequently, the NRC inspector ob-served structural steel installation.
Construction Specification 210.310,
" Structural Steel," establishes the installation requirements for structural steel. Welding was observed to be in accordance with the applicable specification requirements.
Structural steel stud welding and stud welding to concrete embedment plateswere also reviewed. Construction Specification 210.880, " Field Applied Studs," establishes the applicable requirements for field welding of studs.
Installed embedment anchor studs and structural steel shear connections were found to meet the visual acceptance criteria established by this specification.
No violations or deviations were identifie r
-
..
.
.
.
9.
Class IE Electric Equipment Qualification The NRC inspector reviewed the River Bend Final Safety Analysis Report (FSAR) with regard to the environmental qualification program for Class IE equipment, Book 1, " Environmental Qualification Document,"
as well as Section 3.11 of the FSAR were reviewed.
The basis of this review will be utilized in subsequent inspections to establish whether or not qualification programs established by the ven-dors meet the River Bend licensee's commitments as defined in the FSAR.
No violations or deviations were identified.
10.
Management Interviews The RRI met with one or more of the persons identified in paragraph 1 at various times during the inspection period. An exit meeting was held on January 7,1981, with Mr. Philip Graham to discuss various findings and observations made during this inspection period.
~