IR 05000373/1979043
| ML19290E000 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/11/1980 |
| From: | Clint Jones, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19290D993 | List: |
| References | |
| 50-373-79-43, 50-374-79-28, NUDOCS 8002290627 | |
| Download: ML19290E000 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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"FFICE OF INSPECTION AND ENFORCEMENT PIGION III Report No.
50-373/79-43; 50-374/79-28 Docket No.
50-373; 50-374 License No.
CPPR-99; CPPR-100 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60609 Facility Name:
La Salle County Station Units 1 and 2 Inspection At:
La Salle Construction Site (Marseilles, IL)
Inspection Conducted December 12 - 13, 1979
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Inspector:
C. E. Jones
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'e e Approved by:
C. C. Williams, Chief
// //[ b O Projects Section 2
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Inspection Summary Inspection on December 12-13, 1979 (Report Nos. 50-373/79-43; 50-374/79-28):
Areas Inspected: Discussed status of safety related sections of the heating, ventilating, and air conditioning (IIVAC) systems: status of piping in Unit 2 containment and the program for testing the reliability of pumps in the engineered safegaards systems. Reviewed the tendon installation analysis and compared it with designs at other facilities. The inspection involved a total of 17 inspector-hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS
Persons Contacted Principal Licensee Employees
- ll. L. Burke, Site Project Superintendent
- G. E. Groth, Engineer, Station Construction
- B. J. McAndrew, Lead Mechanical Engineer
- R. T. Rose, Project Structural Engineer
- J. D. Dierbeck, Engineer, Station Construction E. R. Wendorf, Engineer Station Construction
- L.
T. Tapella, QA Engineer M. J. Callahan, QA Engineer
- Denotes those personnel attending exit interview.
Program or Functional Areas Inspected 1.
Recirulation Modification The modification is complete in Unit 1 and is scheduled to be complete in Unit 2 in February. None of the modification was inspected during this inspection.
2.
Construction Status The status of various construction work is as follows:
a.
Work has been initiated on the rip-rap measurement.
b.
In Unit 2 erection of large diameter piping, greater than two inches in diameter, is estimated to be 80% complete.
Erection of small diameter piping, two inches and less in diameter, has not been started.
Work on the suppression pool modification has been halted pending c.
receipt of materials and confirmation of final design.
Known modification to Unit 2 is the installation of additional bracing.
Modification to the Unit 1 suppression chamber has been delayed pending completion of preoperational testing and draining of the suppression pool.
3.
Post Tensioning Summary Following the reported failure of the tendon installation at another facility, the licensee informed the inspector of the analysis of tendon design and installation performed at La Salle and the comparison with-2-
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the other facility. The inspectors observations and the licensee's comments are summarized as follows:
a.
Each tendon assembly at La Salle contains 90 wires. The assembly that failed was fabricated with 170 wires. The loading at La Salle is approximately one million pounds while loading on tendon that failed was approximately twice that amount.
b.
Failures that have occurred have been from one heat of metal.
None of this heat was used at La Salle.
In addition, the field anchors for La Salle were fabricated by a different vendor.
c.
The failures that occurred failed within one week of installation.
The tendons at La Salle have been installed for approximately one year and were in place for the structural integrity test.
4.
Heating, Ventillation, and Air Conditioning (HVAC)
The inspector reviewed the status of selected portions of the HVAC, both safety related and non-safety related. Specification J-2590, HVAC work, addendum 1 and 2 specifies the work to be done, requirements to be met, and testing to be done.
Sixteen (16) of the 17 systems listed are 90 - 100 per cent complete.
The inspector toured the diesel generator rooms to observe the HVAC.
The dampers and small amount of duct met requirements of the design drawings. The source of air for the ventilation system is from outside or from the reactor building, and is controlled by temperature and/or radiation monitors.
A summary of the HVAC systems involved and their status is as follows:
System System Safety Percent ID Code Category Complete al.
Auxiliary Building VA Non-safety 90%
HVAC a2.
Control Room HVAC VC Safety Related 90%
a3.
Diesel-Generator VD Safety Related 100%
Room Ventilation Unit I a4.
Auxiliary Electric VE Safety Related 90%
Equipment Room HVAC a5.
Standby Gas Treatment VG Non-Safety Related 100%
for Unit or NSR-3-
a6.
Lake Screen House VII NSR 100%
Ventilation a7.
Machine Shop VJ NSR 100%
Ventilation a8.
c9.
Containment Ventilation for Unit I a10. Primary Containment VQ NSR 100%
Purge for Unit I all. Reactor Building VR Safety Related 95%
Ventilation for Unit I a12. Service Building VS NSR 100%
HVAC System for Units 1 and 2 a13. Turbine Building VT NSR 100%
Ventilation for Unit 1 a14. Radwaste Facility VW NSR 90%
Ventilation System a15. Switchgear Heat VX Safety 100%
Removal Related for Unit 1 a16. Core Standby VY Safety Related 100%
System (CSCS)for Unit 1 Equipment Cooling a17. Auxiliary Building VV NSR 100%
HVAC Equipments Area Ventilation System Unit 1 The work remaining on each system has been compiled on a punch list.
This list varies as work is completed and testing performed.
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The status of the HVAC systems in Unit 2 required for operation of Unit
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I are as follows:
a3.
Diesel-Generator Room VD S f ty 95%
Ventilation Related a9.
Ventilation for Unit 2 a10. Primary Containment Purge VQ NSR 100%
for Unit 2 all. Reactor Building Ventilation VR Safety 50%
for Unit 2 Related a13. Turbine Building Ventilation VT NSR 50%
al7. Auxiliary ' tilding IIVAC VV NSR 50%
Unit 2 a15. Switchgear Heat Removal VX Safety 40%
Unit 2 Related a16. Core Standby Cooling VY Safety 75%
System (CSCS) for Unit 2 Equipment Cooling 5.
Pump Reliability Tests The inspector requested information concerning the status of the pump reliability tests. The licensee provided a status of the pumps and stated that testing was not complete. The pump status as provided on December 12, 1979 was as follows:
Three Unit 2 pumps, 1-LPCS and 2-RHR, are at the factory for a.
testing.
b.
Hours of operation are those compiled to November 20, 1979.
c.
One HPCS pump operated 113.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Since the vibration was stable, the pump will not be shipped off site.
d.
One LPCS pump has operated 211.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> since rework.
Completed 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> reliability test.
e.
PJIR pump, Unit A, has operated 379.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> since rework. This pump :s scheduled to operate 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on it's reliability test.
f.
RHR pump, Unit B, has operated 780.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This pump will be returned for rework when pre-op tests are complete. Rework is for-5-
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a coupling modification. This modification is a change from a screw to a sleeve type coupling and has been completed on the other pumps.
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RHR pump, Unit C, has operated 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> since factory rework.
It has completed the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> reliability test plus 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> opera-tion per operations request.
h.
RRR pump B is in storage af ter Jactory rework. It is scheduled to replace Unit B above.
An analysis of the test program and test data for these pumps will be checked during a subsequent inspection.
This will be done to complete the previously reported unresolved Item No. 373/79-12-01 and 374/79-09-01.
6.
Unit 2 Walk Through The inspector observed the work in progress in Unit 2.
The tour included the major sections of the building from the suppression pool to the fuel storage areas. The general appearance was good.
No items of noncompliance or deviations were noted.
Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted) on December 13, 1979. The inspector summarized the scope and findings of the inspection. The licensee acknowledged the findings as reported.
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