IR 05000335/1981028
| ML20042B469 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/30/1981 |
| From: | Girard E, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20042B464 | List: |
| References | |
| 50-335-81-28, 50-389-81-22, NUDOCS 8203250343 | |
| Download: ML20042B469 (5) | |
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UNITED STATES 8'
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f NUCLEAR REGULATORY COMMISSION
r REGION 11 g
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101 MARIETTA ST., N.W., SUITE 3100 hkt*g
ATLANTA, GEORGIA 30303 g
Report Nos. 50-335/81-28 and 50-389/81-22 Licensee:
Florida Power and Light Company P. O. Box 529100 Miami, Florida 33152 Facility Name:
St. Lucie Docket Nos. 50-335 and 50-389 License Nos. OPR-67 and CPPR-144 Inspection at St. Lucie site near Fort Pierce, Florida -and NRC Office in Bethesda, Mary. land.
Inspect 'r:
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E. H.
irard Dhte 'Si ned Approved by:
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A. R. Herdt, Section Chief D6te Signed Engineering Inspection Branch Engir.aering and Technical Inspection Division SUMMARY
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Inspection on November 2-5 and 9,1981 Areas Inspected This routine, unannounced inspection involved 30 inspector-hours on site and at the NRC Office in the areas of licensee event report on steam generator tube defects (Unit 1) and reactor coolant pressure boundary piping (Unit 2).
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Results Of the two areas inspected, no violations or deviations were identified in one
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area; one violation was found in one area (Violation - Inadequate Corrective Action for Welding Procedure Violations paragraph 6.b).
8203250343 B203ie PDR ADOCK 05000389 G
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REPORT DETAILS I
1.
Persons Contacted Licensee Employees-
- B. J. Escue, Site Manager (Unit 2)
C. M. Wethy, Plant Manager (Unit 1)
R. Frechette, Chemistry Supervisor (Unit 1)
J. H. Barrow, Operations Superintendent (Unit 1)
- R. A. Symes, Senior QA Engineer (Unit 2)
W. F. Jackson, Welding Superintendent (Unit 2)
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- C. W. Sherman, QA Engineer (Unit 2)
J. W. Adams, QA Engineer (Unit 2)
- C. E. Rockwell, QA Engineer (Unit 2)
D. Geller, Mechanical Engineer (Unit 2)
Other Organizations G. Anglehart, Site Representative, Combustion Engineering i
NRC Resident Inspector
- S. A. El rod
- H. E. Bibb
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- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 5, 1981 with those persons indicated in paragraph 1 above. The inspector described the areas inspected and the-inspection finding listed below.
No dissenting comments were received from the licensee.
(0 pen) Violation 389/81-22-01:
" Inadequate Corrective Action for Welding
j Procedure Violations" paragraph 6.b.
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Licensee Action on Previous Inspection Findings i
Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection, i
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Reportable Occurence - Licensee Event Report (Unit 1)
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j (0 pen) LER 81-046: Steam Generator Tubes Eddy Current Testing
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This item was reported to Region II on October 23, 1981.
It concerns steam generator tube degradation. One tube had been identified as baving a small leak in April 1981.
Eddy current testing performed during the current -
refueling outage was directed to tubes in the area of the leak'and identi-fied a number of tube defects in both steam generators. These defects were prompt reportable in accordance with Technical Specification requirements.
The inspector discussed this item with the licensee at the site.
Subse-quently, the licensee presented the results of their investigation of the item, and their proposed future actions, to the NRC in a meeting held in NRC Offices in Bethesda, Maryland, on November 9, 1981.
For the two steam generators (A and B) the licensee reported the following eddy current test results:
INDICATION DEPTHS AS 'o NUMBER OF TUBES NOMINAL TUBE WALL STEAM GENERATOR A STEAM GENERATOR B Ds20"4
17 20*;' Ds40*4
4 D' 40*J
42 Total
63 Total No. of Tubes Tested 3228 2282 Tubes in Each Steam Generator 8519 8519 The licensee's testing indicated that the tubes with indications were limited to tube rows 8 through 12 in each steam generator. It was noted that, based on the number of defects found (i.e., indications exceeding 40?4 nominal tube wall), the Technical Specification requires eddy current testing of all steam generator tubes.
The licensee stated that they believed their data showed that testing already performed had adequately bounded - the defective tubes and a Technical Specification change was proposed to allow them to avoid the complete tube testing for this outage.
The licensee stated that all tubes with indications exceeding 20?4 of wall (30 in steam generator A and 46 in steam generator B), would be plugged.
Region II will examine the licensee's findings for the tube indications in subsequent inspections.
6.
Reactor Coolant Pressure Boundary Piping (Unit 2)
The inspector examined welding related work activities for reactor coolant pressure boundary (RCPB) piping as described below.
The applicable code for the installation of RCPB piping is the ASME B&PV Code,Section III, Subsection NB,1977 Edition through the summer 1977 addenda.
a.
Welding Procedure Specifications and Quality Assurance Procedures
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l The following welding procedure specifications (WPS) were selected and l
reviewed by the inspector:
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WPS PROCESS
FR2 GTAW/SMAW (Manual)
50-R4 GTAW/SMAW (Manual)
Gas Tungsten Arc Welding (GTAW)
Shielded Metal Arc Welding (GMAW)
The above WPS's and their supporting Procedure Qualification Records (PQR) were reviewed to ascertain whether essential and nonessential variables were consistent with code requirements; whether the WPS's were properly qualified and their supporting PQR's were accurate and retrievable; whether all required mechanical tests had Deen performed and the results met the minimum requirements; whether the PQR's had been reviewed and certified by appropriate personnel; and whether any revisions and/or changes to nonessential variables were noted.
The inspector also reviewed the licensee's procedures (SQP-4R3 and SQP-9RI) for preparation, qualification and control of WPS's.to verify that requirements for WPS preparation, qualification, approval /certi-j fication, distribution and revision were adequately specified.
b.
Observation of Welding Activities The inspector observed in process welding activities of RCPB piping.
field welds to determine whether applicable code and procedure require-ments were being met. The welds were examined in process to verify:
proper conduct of work in accordance with a traveler, welder identi-fication and location, welding procedure and assignment, welding r
technique and sequence, materials identity, weld geometry, fit-up, gas purging, preheat, electrical characteristics, shielding gas, welding equipment conditions, interpass temperature, interpass cleaning, process control systems, identity of welders, qualifications of inspection personnel, and weld history records as applicable -to the stage of welding. The welds observed were the following:
WELD JOINT SIZE SYSTEM STAGE OF WELDING CH-0147-002 2" X.344" Chemical Volume Control Repair in progress beyond root RC-0145-001 2" X.344" Reactor Coolant Tacked at fitup for repair RC-0310-001 3" X.438" Reactor Coolant Welding in progress In attempting to verify that the welder (identified FDX) for weld CH-0147-002 was using the proper welding amperage, the NRC inspector asked the welder where he obtained the proper amperage settings.
The welder did not have a copy of the welding procedure but informed the inspector that he knew the proper amperage to use and stated that he had used 50 amps for the root, 60 amps for the hot pass and 75 for the
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remainder with 3/32" 308L filler material.
The welding procedure specified for this repair (on Weld Repair Record 4390) was WPS 43A, Rev. 3, which requires a minimum of 65 amps for the 3/32" filler.
This amperage requirement was apparently violated by the welder for-root and hot pass welding. The inspector. noted that this weld had been completely cut out and was being re-welded by the original welder because of incomplete root fusion, possibly due to inadequate welding amperage. The failure of the welder to comply with the minimum amper-age requirements of the welding procedure is considered a violation of 10 CFR 50, Appendix B, Criterion V.
This violation is identified as item number 389/81-22-01, " Failure to Follow Welding Procedure".
Violations resulting from inadequate compliance with welding procedure requirements have been identified by Region II in two previous inspec-tions this year - violations 389/81-16-01 and 386/81-05-02.
c.
Welding Material Control
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The inspector reviewed the licensee's welding material control proce-dures to determine the adequacy of their requirements for storage, distribution, handling, identification (as acceptable material) and moisture control (including holding and baking).
The procedures reviewed were SQP-3R5 and SQP-8R4.
The inspector verified proper implementation of the above procedures at the rod issue station and
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during the observation of'the welding described in 6.b above.
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Welder Qualification i
The inspector verified the proper qualifications of the welders performing the welds listed in 6.b and the welder specified to perform repair weld SI-0150-003 (aeing ground for repair). The qualifications were verified from the licensee's status list (Welder Qualification Repori and the actual Performance Qualification Records of the four welders.
- Within che areas examined, no violations or deviations were identified except as described in paragraph 6.b.
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