IR 05000382/1983019
| ML20024C230 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/03/1983 |
| From: | Crossman W, Hunnicutt D, Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20024C224 | List: |
| References | |
| 50-382-83-19, NUDOCS 8307120430 | |
| Download: ML20024C230 (3) | |
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APPENDIX U. S. NUCLEAR REGULATORY C0be1ISSION
REGION IV
NRC Inspection Report: 50-382/83-19 Docket:
50-382 Contruction Permit: CPPR-103 Licensee:
Louisiana Power and Light Compnay (LP&L)
-142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection At:
Taft, Louisiana Inspection Conducted: April 28-30, 1983 Inspector:
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Tap y, Reac Inspector Date k[
b d/.f;!83 Approved:
w D. M. Hunnicutt, Chief, Engineering Section Date'
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Approved:
W. A. Crossman, Chief, Reactor Proje'ct Section B Date
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Inspection Summary
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Insoection Conducted April 28-30, 1983, (Report 50-382/03-19)
Areas Inspected:
Special announced inspection: involving review and witnessing of containment integrated leakage rate test.' The inspection' involved 28 inspec-
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' tor-hours onsite by one NRC inspector.
Results: Within the area inspected, no violations,or deviations were identified.
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8307120430 830606 PDR ADDCK 05000302
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DETAILS
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Persons Contacted
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Principal ' Licensee Personnel
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D..Grubic, Start-up QA Engineer J.l Saith, Start-up QA Engineer f;
I. Smith, Start-up Engineer
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S.-Silverman, Start-up Engineer Other Personnel
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S. Nayak, ILRT Test Director, Shantheri Services, Inc.
E. Dillon, Assistant Chief Engineer, Ebasco Services, Inc.
E. Franklin, Project Engineer, Ebasco Services, Inc.
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2.
Containment Interarated Leakage Rate Test p,
The first periodic Reactor Containment Integrated Leakage Rate Test (ILRT)
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at Waterford. Steam Electric. Station, Unit 3, was addressed during this inspection.
The inspection included observations, procedure and records
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.. review, and independent calculations by the NRC inspector. ~This inspection effort was performed to ascertain whether the testing was con -
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ducted in accordance with approved procedures _and specified acceptance criteria.
Specific requirements are contained in the following documents:
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10 CFR, Part 50, Appendix J, " Primary Reactor Containment Leakage -
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Testing for Water-Cooled Power Reactors"
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ANSI'N45-4-1972, " Leakage-Rate Testing of Containemnt Structures for i
Nuclear Reactors" l
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Waterford Steam Electric Station, Unit 3, Technical Specifica-(
tion 3/4.6.1.2 l
Startup Integrated Test Procedure No. SIT-TP-150, " Containment Intergrated Leak Rate Test," Revision 1, incorporates the requirements
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into the test procedure.
This procedure was reviewed by the NRC inspector.and no discrepancies from the specified requirements were L
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The instrument calibration certifications' traceable to the US Bureau I-lof.Standardsfortheresistancetemperaturedetectors,humiditymeasuring
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devices, pressure gauges, and the flowmeter used in the verification test l'
were' reviewed.
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During the performance of the type "A" test, the NRC inspector computed the leakage rate in accordance with the Mass Point Data Analysis Absolute Method technique of the American Nuclear Society Standard No. 56.8-1981,
" Containment System Leakage Testing Requirements." The computations performed by the NRC inspector were used to compare with the licensee's results for the purpose of verifying the calculational procedure and confirming the results.
This analytical technique confirmed the acceptability of the results being obtained by the licensee's contractor, Ebasco Services Inc.
The NRC inspector witnesssed portions of the entire reduced pressure test which was conducted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a pressure of 22 psig, and the six hour confirmatory imposed leakage test.
Fourteen hours and 45 minutes of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> full pressure (44 psig) test were reviewed by the NRC. inspector.
The independent calculations by the NRC inspector consisted of determining the mass of air in the containment, utilizing the ideal gas law, at each time point during the test and subsequently performing a straight line least squares analysis to estimate the leakage rate. The analysis results in a statistically determined estimation of the projected 24-hour leakage rate. The NRC inspector found that the test data showed,' with a 95 percent level of confidence, that the measured leakage rate was well below the allowable leakage rate of one-half of 1 percent per day by weight of containment air when computed using 59 data points.
This analysis confirmed the acceptablity of the test results being obtained by the licensee.
From a review of the official test log, the NRC inspector.also verified that closed systems inside the containment which are normally filled with water during postaccident conditions were nonvented to accordance with 10 CFR Part 50, Appendix J requirements.
The result of local leak tests (type "B" and "C" tests) were also reviewed during this inspection.
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Exit Interview
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TheNRCinspectormetwiththeILRTteskdirectorat:theconclusionof,-
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the inspection and summarized the scope'and' findings o? the inspection.
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