IR 05000382/1979016
| ML19257A835 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/23/1979 |
| From: | Crossman W, Randy Hall, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19257A832 | List: |
| References | |
| 50-382-79-16, NUDOCS 8001080692 | |
| Download: ML19257A835 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-382/79-16 Docket No. 50-382 Category A2 Licensee:
Louisiana Power and Light Company 142 Delnronde Street New Orleans, Louisiana 70174 Facility Name:
Waterford Steam Electric Station, Unit No. 3 Inspection at: Waterford Site, Taft, Louisiana Inspection Conducted: October 30-31 and November 1-2, 1979 l
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/7E Inspectors:
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g..s R. C. Stewart, ~ Reactor Inspector, Projects Section
'Date
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(Paragraphs 1, 2, 3, 4, 5, 6, 8 and 9)
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L. D. Gilbert, Reactor Inspector, Engineering Date
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Support Section (Paragraph 7)
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Approved-
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///If h1 W. A. Crossman, Chief, Projects Section
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// 3 ?f R. E. Hall, Chief, Engineering Support Section Date' /
Inspection Summary Inspection on October 30-31 and November 1-2, 1979 (Report No. 50-382/79-16)
Areas Inspected: Routine, unannounced inspection of construction activities related to a follow-up review of the in process welding activities on the reactor coolant pressure boundary piping; visual examination of welds on steel structures and supports in the reactor containment; and a follow-up review of actions taken with regard to previously identified inspection findings. The inspection involved fifty-two inspector hours by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
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Principal Licensee Employees
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Gerrets, QA Manager
- B. Brown, QA Engineer
- C. Chatelain, QA Engineer
- J. Woods, QA Engineer
- C. Decareaux, Project Coordinator
- B. Toups, QA Engineer' Technician Other Personnel
- J. Crnich, Site Manager, Ebasco
- R. Milhiser, Project Superintendent, Ebasco E. Breedlove, Tompkins-Beckwith (T-B)
- R. Hartnett, QA Site Supervisor, Ebasco
- J. Britt, Site Manager, Nuclear Installation Services Company (NISCO)
- D. Shah, QC Engineer, NISCO W. Barthle, Piping Superintendent, NISCO J. Ball, Welding Engineer, NISCO The IE Inspectors also interviewed other licensee and contractor personnel including members of the engineering and QA/QC staffs.
- Denotes those attending the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Construction Deficiency Reports (CDR)/Part 21 Report, dated May 10, 1979, June 29, 1979, and August 31, 1979: Material Failure 4 inch 45 ell and 4 inch 90 ell.
As indicated in the initial CDR, the manufacturer of the ells had initiated a recall program on the 4 inch fittings due to a high carbon content in a specific heat of steel. Ten of the 4 inch ells were supplied to the Waterford 3 site. Nine were located and removed from the site and the remaining one, a 4 inch 45 ell, is determined by the licensee to have been scrapped.
During this inspection, the IE inspector reviewed the methods employed by the licensee in establishing that the missing ell was scrapped.
The licensee demonstrated the systems used in conducting a search of all material storage areas; a records review of all four inch piping systems, both safety and non-safety; and a walk down of all four inch piping systems.
In addition, the licensee has established an additional veri-fication check to be accomplished during the system turn-over prior to the system hydrcstatic test.
The IE inspector had no further questions regarding this CDR.
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(Closed) Unresolved Item (50-382/79-02):
Structural Steel Pressurizer Support. During this inspection, the IE inspector reviewed the QA/QC records documentation regarding the weld repairs made on the pressurizer support structure and identified in the Nonconformance Report (NCR)
No. W3-1160.
The records indicate that all repairs were accomplished in accordance with the applicable codes and licensees QA/QC program requirements.
The IE inspector had no further questions regarding this matter.
3.
Site Tour The IE inspectors walked through various construction and storage areas to observe construction activities in progress and to inspect the general state of cleanliness and adherence to housekeeping requirements.
No items of noncompliance or deviations were identified.
4.
Reported Construction Deficiency - Reactor Containment Penetrations 3 & 4
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During this inspection, the IE inspector was informed of a reportable construction deficiency related to the vendor supplied feedwater penetration assemblies 3 and 4.
During the material certification verification check conducted by EBASCO QA, it was discovered that portions of the assembly material had not met the impact test requirements of Subsection NE, ASME,Section III.
The assemblics have not been installed and have been returned to the vendor for corrective repair. The licensee will submit a written report on the matter in accordance with 10 CFR 50.55(e).
This matter will be considered unresolved pending NRC review of the licensee's final report.
5.
Potential Construction Deficiency - NAMCO EA-180 Limit Switches During this inspection, the licensee infonned the IE inspector of a possible malfunction of the NAMCO's EA 180 series limit switches being utilized in the HVAC system components.
The top cover gaskets from a production lot will emit vapor at temperatures above 175 F, possibly causing a switch malfunction.
The licensee will submit a written report in accordance with 10 CFR 50.55(e) requirements.
This matter is considered unresolved pending NRC review of the final report.
6.
Steel Structures and Supports - Visual Examination of Welds During this inspection, the IE inspector conducted a visual exami-nation of welds completed on the reactor coolant pump support struc-tures IA, IB, 2A, and 2B.
In additional, examination was made on the pressurizer support structure. The examinations were made on a random basis and in accordance with applicable codes and NRC procedures.
1705 129 No items of noncompliance or deviations were identified.
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7.
Reactor Coolant Pressure Boundary Piping The IE inspector reviewed the NISCO material control program for welding filler material to be used in welding the Reactor Coolant Pressure Boundary (RCPB) piping for compliance with the storage and handling requirements of NISCO Procedure ES 56, Revision C.
The pressurizer surge line was also inspected for compliance with the storage and receiving inspection requirements of NISCO material control Procedure ES 63, Revision C.
The IE inspector observed the repair welding of field weld P5W1, NISCO Drawing 3015-003 and reviewed the material certification of the type 308 filler material used in making the repair for compliance with ASME,Section III requirements. The qualification of the welder doing the repair welding was reviewed for compliance with ASME,Section IX requirements.
The IE inspector reviewed the postweld heat treatment records for two completed RCPB field welds, P1W1 and P1W2 on NISCO Drawing 3015-003, for compliance with the general specification for postweld heat treatment of nuclear components, Procedure ES 3016-1, Revision A.
The surface condition of four RCPB pipe welds (P1W1, P1W2, P5W2 and P9W2) was inspected for compliance with the visual examination requirements of NISCO Procedure ES 100-5, Revision C.
No items of. noncompliance or deviations were identified.
8.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. One item relating to penetrations 3 and 4 is identified in paragraph 4 and one item relating to limit switches is identified in paragraph 5.
9.
Exit Interview The IE inspectors met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on November 2, 1979. The IE inspector summarized the purpose and the scope of the inspection and the findings.
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