IR 05000373/1980011
| ML19323A984 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/19/1980 |
| From: | Clint Jones, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19323A979 | List: |
| References | |
| 50-373-80-11, 50-374-80-07, 50-374-80-7, NUDOCS 8005090072 | |
| Download: ML19323A984 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION l
s 0FFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report Nos. 50-373/80-11; 50-374/80-07 Docket Nos. 50-373; 50-374 License Nos. CPPR-99; CPPR-100 Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility Name:
La Salle County St.' tion, Units I and 2 Inspection At:
La Salle Construction Site (Marseilles, Illinois)
Inspection Conducted: March 6-7, 1980 ('A'yk-su r'
3[/f[Yb Inspector:
C. E. Jones d2gM%
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Approved By:
C. C. Williams, Chief, 3//7 !E d Projects Section 2 (
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Inspection Summary Inspection on March 6-7, 1980 (Report No. 50-373/80-11; 50-374/80-07)
Areas Inspected: Status of the heating, ventilating, and air conditioning (HVAC) system: review of the nonconformance reports issued by the HVAC con-tractor. Observed work in progress concerning modifications to upgrade the strength of the suppression pool and reactor pedestal, Unit one. The t.ork was being done to confrom with approved design changes.
Results: No items of noncomplian: e or deviations were identified.
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DETAILS
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Persons Contacted Principal Licensee Employees
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- L. J. Burke, Site Project Superintendent
- U. E. Groth, Engineer, Station Construction
- R. T. Rose, Prosect Structural Engineer J. T. Dierbeck, Engineer, Station Construction
- T. Quaka, Quality Assurance Supervisor M. J. Callahan, QA Engineer
- L. T. Tapella, QA Engineer Other Personnel C. Baumgartner, Zack Company Site Superintendent
- M. R. Dougherty, Walsh Construction Co., QA Supervisor
- Denotes those personnel attending the exit interview.
Program or Functional Areas Inspected 1.
Heating, Ventilating, and Air Conditioning (HVAC)
The inspector visited the Auxiliary Building and Control Rooms.
The licensee and contractor called the inspector's attention to certain I
minor design changes or modification to be made to clear interference with other equipment and electrical conduits, most of the fire protec-tion insulation has been installed. The licensee estimated these
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modifications would be completed by May or June. This would include clearing a portion of the NCR's.
i In addition, the inspector reviewed the nonconformance log. A total of 60 nonconformance reports have been issued of these 32 remain open.
A major portion of these NCR's concern hangers. The problems vary from improperly placed hangers to poor or improperly placed welds. The li-censee indicated several of these NCR's would be cleared since the welders are working in this area. Also, he stressed that deficiencies were being corrected as the inspection of the (HVAC) system continues.
The inspector stated that the (HVAC) system would continue to be con-sidered as an unresolved item pending clearance of open NCR's and subsequent inspection.
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Suppression Pool Modifications The inspector toured the Unit I suppression pool and observed the work in progress. The contractor was removing the pool liner as required by'the revised design. The concrete under the liner plate appeared solid, well compacted and no evidence of honeycomb was visible in the-2-
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areas observed.
Construction drawings specify the removal of 54 sec-
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tions of liner plate in the pool wall and 31 from the reactor pedestal external liner. The inspector observed the concrete surface from which approximately 15 percent of the liner plate had been removed.
The concrete in the original pedestal openings indicated some sanall voids at the outside perimeter of the four ten feet four inch openings that were closed.
Since the fill concrete for the pedestal
was not considered as structural concrete, the small voids were not considered significant.
In addition, the latest revision requires bracing to be used in the suppression pool.
Special precautions are being taken to insure the core drilling and placement of anchor bolts complies with the specifications. These are shown on structural drawings.
The inspector also reviewed the quality records for the concrete used in the reactor pedestal. The QC records were complete and in order. According to test results indicated in the records reviewed, concrete strengths were in excess of 4000 psi.
No items of noncompliance or deviations were obse m d in this area.
Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on March 7, 1980. The inspector summarized the scope and findings of the inspection.
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