IR 05000373/1979035
| ML19260C081 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/05/1979 |
| From: | Lee E K, Neisler J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19260C079 | List: |
| References | |
| 50-373-79-35, 50-374-79-24, NUDOCS 7912180342 | |
| Download: ML19260C081 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-373/79-35; 50-374/79-24 Docket No. 50-373; 50-374 License No. CPPR-99; CPPR-100 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: La Salle County Station, Units 1 and 2 Inspection At: La Salle Site, Marseilles, IL Inspection Conducted: October 16 and 17, 1979 l,TVil5 wv1 ' v~~-
t Inspectors: / E. W. K. Lee
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J. H. Neisler
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C.C.ailliams,l Chief 0 [_.
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Projects Section 2 Inspection Summary Inspection on October 16 and 17, 1979 (Report No. 50-373/79-35; 50-374/79-24)
Areas Inspected: Verified ASME Certificates of Authorization held by licensee and contractors. Review of previously reported items. Observation of work activities relative to safety related piping, Unit 2.
Observation of work activities relative to modifications on suppression pool and reactor recircu-lation system, Units 1 and 2.
The inspection involved a total of 17 inspector-hours by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted Principal Licensee Employees
- L. J. Burke, Site Project Superintendent R. T. Rose, Project Structural Engineer D. J. Skoza, QA Engineer
- T. E. Quaka, QA Supervisor
- D. A. Spencer, QA Engineer
- T. R. Sommerfield, QA Engineer
- B. J. McAndrew, Lead Mechanical Engineer K. Steele, Lead Electrical Engineer E. E. Falb, Field Engineer
- G.
E. Groth, Station Construction
- J. W. Gieseker, Station Construction L. J. Tapella, QA Engineer
- A. Mayhan, QA Engineer Contractor and Other Personnel
- R. C. Schulz, QC Supervisor, Morrison Construction Company
- M. F. Whenny, Welding QC Supervisor, Morrison Construction Company
- K. Kranz, Welding, Morrison Construction Company R. Ouzts, QA Manager, H. P. Foley Company
- Denotes those attending exit interview.
Licensee Action on Previously Reported Items (Open) Reported 10 CFR 50.55(e) item (373/78-XX-03; 374/78-XX-04):
Licensee reported deficiencies in dimensional tolerances on RHR, HPCS and LPCS pumps. Unit 1 LPCS pump has completed a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> test.
RHR pump A 400 hour0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> test is in progress. RHR pump C is being installed. RHR pump B to be rett;ned to factory for coupling repairs. Unit 2 RHR and LPCS pumps have been returned to factory for rework.
This item remains open until all reported deficiencies have been corrected.
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Section I
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Prepared by J. H. Neisler Reviewed by C. C. Williams, Chief Projects Section 2 1.
Review of ASME Certificates of Authorization Pursuant to TI 2512/3, Inspection Requirements to Verify Compliance with ASME Certification System Requirements, the inspector reviewed licensee and contractor Certificates of Authorization as follows.
a.
Commonwealth Edison Company N-Certificate Number N-2020 expiration date: February 3, 1981.
b.
Morrison Construction Company NA-Certificate Number N-1621, corporate and N-1621-1, site.
NPT-Certificate Number N-1622, corporate and N-1622-1, site.
Morrison Construction Company's certificates expire during January 1980, however, an ASME survey for certificate renewal is scheduled to be conducted November 5-9, 1979.
c.
Reactor Controls Incorporated NPT-Certificate Number N-1299-4; expiration date:
January 9, 1981.
d.
General Electric Company NA-Certificate Number N-2200 expiration date: October 13, 1981.
NA-Certificate Number N-2201 expiration date: October 13, 1981.
No items of noncompliance or deviations were identified in the above area.
2.
Plant Status The inspector reviewed status of Unit I construction with site manage-ment personnel.
Unit I currently reported as being 92% complete.
Listed below are licensee's estimate of work remaining in some critical areas.
a.
Electrical (1) Cables; 13,506 pulled 1,234 coiled, 631 remain to be pulled.
Cables Unit 2 to be pulled prior to Unit I fuel load; 2,340 pulled, 135 coiled, 775 remain to be pulled.
Present cable pull rate is approximately 153 per week.
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(2) Terminations; Unit 1; 28,980 complete, 1,680 remain to be
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completed. Unit 2 to complete prior to Unit I fuel load; 1,500 complete, 4,000 remain to be completed.
Present termination rate is approximately 300 per week.
(3) Conduit installed 247,500 feet. To be installed 51,500 feet. Present rate of installation is approximately 10,000 feet per month.
(4) System turnover: 52 systems turned over, 18 systems under test.
b.
Fire proofing:
96% complete.
c.
Fire seals at pipe penetrations:
Silicone foam 70% complete.
Lead; 95% complete.
d.
In-service inspection baseline data is reported at 90% complete.
3.
Modifications Reactor Recirculation System nozzle safe end/ thermal sleeves a.
have all been cut off and are being prepared for welding the modified safe end/ thermal sleeves to the nozzles. Welding is expected to begin next week.
b.
Suppression pool work is expected to resume next week when CBLI return to the site. The inspector performed a visual inspection of the one KWU quencher that has been received to date. No visual indications of welding deficiencies were noted.
No items of noncompliance or deficiencies were identified in the above areas.
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Section II
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Prepared by E. W. K. Lee Reviewed by D. H. Danielson, Chief Engineering Support Section 2 1.
Safety Related Piping - Observation of Welding Activities (Unit 2)
The inspector observed the welding of Main Steam System weld No.
WMS-450 on traveler No. MS-T319.
It was determined that (1) work was conducted in accordance with traveler; (2) proper welding materials were used; (3) welding procedure requirements were met; (4) work area was free of weld rod-stubs and; (5) physical appear-ance was acceptable.
No items of noncompliance or deviations were identified.
2.
Reactor Coolant Pressure Boundary Piping - Postweld Heat Treatment (Unit 2)
a.
Review of Procedure The inspector reviewed Morrison Construction Company procedure No. 1-3-1LS, Revision 2, " Heat Treating Procedure." It was determined that the procedure met the ASME and PV Code requirements.
b.
Observation of Work Activities The inspector observed the postweld heat treatment of the Feedwater System, line No. 2FWO2FB-24", weld No. FW249 and line No. 2FWO2CB-24", weld No. WF230.
It was determined that (1) weld area is instrumented to provide time-temperature recordings; (2) temperature recorder and thermocouples are calibrated and certified; (3) placement of thermocouples are in accoraance with the procedure; (4) heatup rate met the pro-cedure and code requirements and (5) personnel performing the work are qualified.
No items of noncompliance or deviations were identified.
Exit Intervie__w The inspectors met with licensee representatives (denoted under persons contacted) at the co :lusion of the inspection. The inspectors summarized the purpose and scope of the inspection.
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