ML20030B981
| ML20030B981 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/21/1981 |
| From: | Gilbert L, Randy Hall, Whittlesey K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20030B977 | List: |
| References | |
| 50-382-81-17, NUDOCS 8108250283 | |
| Download: ML20030B981 (3) | |
See also: IR 05000382/1981017
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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Report:
50-382/81-17
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Docket:
50-382
Category A2
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Licensee: Louisiana Power and Light Company
142 Delaronde Street
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New Orleans, Louisiana 70174
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Facility Name: Waterford Steam Electric Station, Unit 3
Inspection at: Waterford Site, Taft, Louisiana
Inspection Conducted: July 6-10,1981
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Inspectors:
. D. Gilbert, deactor Inspector, Engineering and Materials
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Section (Paragraphs 1-6)
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K. A. Whittlesey, React 6r Inspector - Trainee, Engineering
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and Materials Section
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Approved:
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Da'te '
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R. E. Hall, Acting Chief, Engineering and Materials
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Section
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Inspection Summary
Inspection on July 6-10,1981 (Report 50-382/81-17)
Routine, unannounced inspection of construction activities
Araas Inspected:
related to w'eTding of Containment Vessel and Reactor Coolant Pressure Boundary
piping. The inspection involved 60 inspector-hours by two NRC inspectors.
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In the two areas inspected, no violations or deviations were identi-
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Results:
One violation was identified in the area of containment
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fied in one area.
welding (violation - failure to follow procedures - paragraph 3).
8108250283 810724
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PDR ADOCK 05000382
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DETAILS
1.
Persons Contacted
Principal Licensee Employees
- L. L. Bass, Project QA Engineer
- B. M. Toups, QA Engineering Technician
Other Personnel
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- J. DeBruin, ESSE Project Engineer, Ebasco
P. Vucelich, Corporate Welding Engineer, Chicago Bridge and Iron (CB&I)
L. Nunez, Project Welding and QA Supervisor
M. Folsom, Field QA Manager, Nuclear Installation Services Company
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(NISCO)
The NRC inspectors also interviewed other licensee and contractor per-
sonnel including members of the engineering and QA/QC staffs.
- Denotes those attending the exit interview.
2.
Site Tour
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The NRC inspectors walked through the Reactor and Auxiliary Buildings
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to oberve construction activities in progress and to inspect for
housekeeping.
No violations or deviations were identified.
3.
Reactor Containment Vessel
The NRC inspectors observed activities relrted to welding Weld Joint G
of Drawing 26 using Repair Procedure RP, Revision 2 for reinstallation
of the Containment Vessel Equipmer.t Hatch Cover.
Electrodes used for
welding were consistent with Welding Procedure WPS E7018/71-2426 and
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traceable to certified material test reports.
However, control of unused
electrodes was not consistent with Section 8.0 to Division 4 of the CB&I
Nuclear Quality Assurance Manual for ASME Section III Products, Issue
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No 6, in that, the NRC inspectors observed several unused welding elec-
trodes in a bucket and one on the floor in the CB&I work area after the
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end of the work shift.
It was also observed the next morning that the
rod had neither been returned to the storage ovens, destroyed by bending,
nor removed from the work area and discarded to preclude inadverent use.
The NRC inspectors also detennined that reinstallation of the Equipment
Hatch Cover was classified by CB&I as a nonconformance/ repair, but the
work activity had neither been entered on the Nonconformance Control
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List nor was it contrcRd and documented on a Repair Check List as
required in Section l',.0 to Division 4 of the CB&I Quality Assurance
Manual.
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These two examples of failure to follow procedures are an apparent
violation of 10 CFR 50, Appendix B, Criterion V.
4.
Reactor Coolant Pressure Boundary Pipino
The NRC inspectors reviewed the post weld heat treatment records for
three field welds in the Reactor Coolant Pressure Boundary piping:
Welj P16Wl, Weld P16W2, and Weld P10W1 on Drawing 3015-003.
The post
weld heat treatments for Weld P16W1 and Weld P16W2 were consistent
with requirements of Welding Procedure WPS 10.1.14 and Heat Treataent
Procedure ES 3016-1.
During review of the post weld heat treatment
records for Weld P10Wl, the NRC inspectors were informed that a Noncon-
formance Report, NISCO 050, Revision 1 had been issued because the
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time and temperature limitations for heat treataent had been exceeded.
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The nonconformance report was reviewed and the status discussed with
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Ebasco.
This item is considered unresolved pending final disposition and review
of the nonconformance report.
5.
Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items, violations,
or deviations. An unresolved item related to Reactor Coolant Pressure
Boundary piping is discussed in paragraph 4.
6.
Exit Interview
The NRC inspectors met with licensee representatives (denoted in
paragraph 1) and J. E. Cummins (NRC Resident Reactor Inspector) on
July 10, 1981, and summarized the purpose and findings of the inspection.
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